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Eliminating Typos,Providing Addl Clarification,Improving Consistency & Deleting Administrative Stipulations/Allowances No Longer in Effect at Plant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 PAGE

1. 0 DEFINITIONS

1. 1 ACTION.

1.2 AXIAL SHAPE INDEX ~ ~ ~ ~ ~

1.3 AZIMUTHAL POMER TILT - Tq.

1.4 CHANNEL. CALIBRATION.

1.5 CHANHEL CHECK...

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

1.7 CONTAINMENT INTEGRITY...

1.8 CONTROLLED LEAKAGE.................. 1-2 1.9 CORE ALTERATION.................

1. 10 DOSE EQUIVALENT I-131...................... 1-3 E-AVERAGE DISINTEGRATION ENERGY............

l. 12 EHGIHEERED SAFETY FEATURES RESPONSE TIME

l. 13 FREQUENCY NOTATION,................. 1" 3

l. 14 GASEOUS RADMASTE SYSTEM. 1-3

1. 15 IDEHTIFIEO LEAKAGE........ 1-3

1. 16 Kt ~ w ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ 1-4

l. 17 MEMBER(S) OF THE PUBLIC........... 1-4

1. 18 OFFSITE DOSE CALCULATION MANUAL ( ).. 1-4

1. 19 OPERABLE " OPERABILITY..

1.20 OPERATIONAL MODE MODE......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

l. 21 PHYSICS TESTS...........

1. 22 PLANAR RADIAL PEAKING FACTOR " F 1-4 XP

l. 23 PRESSURE BOUNDARY LEAKAGE.......... 1-5 1.24 PROCESS CONTROL PROGRAM (PCP)...... 1-5

l. 25 PURGE - PURGING..............

l. 26 RATED THERMAL POMER.. . ........ .. ~ ~ ~ ~ ~ 1" 5

1. 27 REACTC:~ TRIP SYSTEM RESPONSE TIME. 1" 5

1. 28 REPORT 'LE EVENT....... 1-5

1. 29 SHUTDGi'N MARGIN.. 1" 6

1. 30 SITE BOUNDARY,... 1-6 9010170227 901011 P13R ADOCK 05000528 P PDC PALO VERDE - UNIT 1 AMEHDMEHT HO 23

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INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS ACTION ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ ~ ~ ~ ~

1.2 AXIAL SHAPE INDEX..............:....

1.3 AZIMUTHAL POWER TILT - T .

1.4 CALiBRATION.......................

q'HANNEL 1.5 CHANNEL CHECK.

1.6 CHANNEL FUNCTIONAL TEST...... 1-2 1.7 CONTAINMENT INTEGRITY . 1"2 1.8 CONTROLLED LEAKAGE................

1.9 CORE ALTERATION 1"2 1.10 DOSE E(UIVALENT I-131 ............................... lee3 1.11 K " AVERAGE DISINTEGRATION ENERGY.. 1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME............. 1"3 1.13 FRE(UENCY NOTATION........................ 1"3 1.14 GASEOUS RADWASTE SYSTEM...........-...............-.. 1-3

1. 15 IDENTIFIED LEAKAGE.. 1-3 l.a6 K" N 1 e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1-4 1.17 MEMBER(S) QF THE PUBLIC......... lee4 1.18 OFFSITE DOSE CALCULATION MANUAL (0 ) 1-4 1.19 OPERABLE - OPERABILITY............................... 1-4 1.20 OPERATIONAL MODE - MODE..................................... 1-4 1.21 PHYSICS TESTSe ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ ~ ~ ~ ~ ~

1.22 PLANAR RADIAL PEAKING FACTOR- 1-4 1.23 PRESSURE BOUNDARY LEAKAGE..........................,. 1-5 1.24 PROCESS CONTROL PROGRAM (PCP),.... 1"5 1.25 PURGE " PURGING................. 1-5 1.26 RATED THERMAL POWER.... 1-5 1.27 REACTOR TRIP SYSTEM RESPONSE TIME .

'1.28 REPORTABLE EVENT..... ~ ~ a-5 1.29 SHUTDOWN MARGIN......... 1-6 1.30 SITE BOUNDARY PALO V~~DE - UNIT 2 AMENDMENT NO. 13

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GlilLY FOR )NFORRlATION 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 are based on steam generator differential pressure.

Floor.'etpoints (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) Irange of the distance between instrument nozzles.

steam generator upper and lo~er level narrow

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INOEX LIRITIHG"CONBITIGHS-+OR-OPERATION-AHD-SURVEI-I LANCE RE UIR'EMENTS SECTION PAGE 3/4.10.4 CEA POSITION, REGULATIHG CEA INSERTION LIMITS AND REACTOR COOLANT COLD LEG TEMPERATURE........ 3/4 10-4 3/4. 10. 5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY........ 3/4 10-5 3/4. 10.6 SAFETY INJECTION TANKS 3/4 10-6 3/4. 10. 7 SPENT FUEL POOL LEVEL ..... 3/4 10-7 3/4. 10.8 SAFETY INJECTION TANK PRESSURE . 3/4 10-8 3/4.10.9 SHUTDOWN MARGIN AND K " CEDMS TESTING................ 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... 3/4 ll-l DOSE 3/4 11-5 LIQUID HOLDUP TANKS. ~ .. ~ - . ~ ~ . - .,- - - - - ~ - ~ - ~ ~ - . ~ ~ - .. ~ 3/4 11-6

.3/4.11.2 GASEOUS EFFLUEHTS DOSE RATE ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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 .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 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 11-16 3/4. 11. 4 TOTAL DOSE. 3/4 11-18 3/4. 12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4. 12. 1 MONITORING PROGRAM. 3/4 12-1 3/4.12.2 LAND USE CENSUS..... 3/4 12-11 3/4. 12. 3 INTERLABORATORY COMPARISOH PROGRAM. 3/4 12-12 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. a

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With a Reactor Coolant System oper ating loop temper ature (Tcol1 d) d less than 552'F, restore Tcold ld to within its limit within 15 minutes or be in HOT STANDBY within the next 15 minutes.

SURVEILLANCE RE UIREMENTS 4.1.1.4 The Reacto'r Coolant 'Sys'em'emperature (T d) shall be determined to be greater than or equal to 552'F:

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.a. Within 15 minutes prior to achieving reactor criticality, and b.'t least t

once per 30 minutes when the reactor is critical and the r Reactor Coolant System T ld is les's than 557 F.

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than or equal to 1.0.

¹With f greater e

K eff "See Special Test Exception 3. 10.5.

PALO VERDE " UNIT 1 3/4 1-6

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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. Within 15 minutes prior to achieving reactor criticality, and b.. At, least.;-once per 30 minutes'hen the reacto'r is critical and the Reactor Coolant System Tcold ld is less than 557'F.

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

CGIMTIRGLLED O'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 (Tcold ld) less than 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 ld is less than Reactor Coolant System T 557'F.

With Keff greater than or equal to 1.0.

See Special Test Exception 3.10.5.

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

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GOP4 fRGiL,LFD BV USFR P.6 JAN 13 '89 14:46 APSiUHET 3 s

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' IVI THI INC C OHTAO NOIT EHS 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.

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 lNFQRMATION ONLY

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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

II ACTION: ( Cont ~'nued }

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 .

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.

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 hours.

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

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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 hour 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

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FOR lNFORMATjON ONLY 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

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CGWTRGLLED B'Il'SER

'RE'ACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS 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, in the previous 7 days.

if not performed (2) 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 nuclear signals to agree with the calorimetric if absolutepower CPC calculation 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.

(3) 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.

(4)- Neutron detectors may be excluded fr'om CHANNEL CALIBRATION.

(5)- 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 these" el ements.'-

shall'9'e (6)- 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.

(7)- 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.

(s) .. 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.

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

(1O)- 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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TABLE 4. 3-1 Continued 0 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS 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, in the previous 7 days.

if not performed (2) 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.

(3) 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.

(4)- Neutron detectors may be excluded from CHANNEL CALIBRATION.

(5) 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.

(6) 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.

(7) 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 0 of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage and shunt trips.

- UNIT PALO VERDE 3 3/4 3-16

0 0 0 TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM/TRIP MEASUREMEHT INSTRUMENT OPERABLE MODES SETPOTNT RANGE ACTION Area Monitors A. Fuel Pool Area RU-31 <15mR/hr 10-~ to 10~mR/hr 22 & 24 B. New Fuel Area RU"19 <15mR/hr 10-~ to 10~mR/hr 22 C. Containment RU-148 &

RU-149 1,2,3,4 <10R/hr 1R/hr to 107R/hr 27 D. Containment Power Access Purge Exhaust RU-37 &

RU-38 <2.5mR/hr 10-~ to 1 - mR/hr 25 E. Main Steam

1) RU-139 A8B 1,2,3,4 10 to 10 mR/hr 27

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

2. Process Monitors A. Containment Building Atmosphere RU-1 1P2P3P4 23 8 27

1) Par ticul ate <2.3xlO- pCi/cc 10-9 to 10-~pCi/cc Cs"137

2) Gaseous. <6.6x10- pCi/cc 10- to 10- pCi/cc Xe" 133 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.

TABLE 3.3-6 RAOIATION MONITORING INSTRUMENTATION MINIMUM CMANNELS APPLICABLE ALARM/TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION Area Monitors A. Fuel Pool Area RU-31 <15mB/hr 10-~ to 10~mR/hr 22 8 24 B. New Fuel Area RU-19 <15mR/hr 10-~ to 10~mR/hr 22 C. Containment RU-14& 8 RU"149 1,2,3,4 <10R/hr 1R/hr to lO~R/hr 27 D. Containment Power Access Purge Exhaust RU-37 8 RU-38 <2 5mR/hr 10-i to 1 - mR/hr 25 E. Hain Steam

1) RU-139 A8B 1,2,3,4 10 to 10 mR/hr 2?

2) RU-140 ABB 1,2,3,4 10 to 10 mR/hr 27

2. Process Monitors A. Containment Building Atmosphere RU-1 1,2,3,4 23 4 27

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

2) Gaseous <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.

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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: 1 and 2.

MODES 9

ACTION:

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~~<) <

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-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. 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 1 3/4 3-48 AMENDMENT NO. 27

'IN kn

.fI

~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.

APPLICABILITY: MODES 1 and 2.

l 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 .

b.

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

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 REMOTE SHUTDOWN DISCONNECT SWITCHES SWITCH DISCONNECT SWITCHES LOCATION SG 1'line 2 Atmospheric Dump Valve Solenoid Air RSP Isolation Valves SGB-HY-178A and SGB-HY-178R

2. SG 2 line 1 Atmospheric Dump Valve Solenoid Air RSP Isolation Valves SGB-HY-185A and SGB-HY-185R

3. Auxiliary Spray Valve RSP CHB-HV"203 Letdown to Regenerative RSP Heat Exchanger Isolation, CHB-UV-515

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

e. Auxiliary Feedwater Pump RSP B to SG 1 Control Valve', AFB-HV-.30

7. Auxiliary Feedwater Pump RSP B to SG 2 Control Valve, AFB-HV-31

8. Auxiliary Feedwater Pump RSP B to SG 1 Block Valve, AFB-UV-34

9. Auxiliary Feedwate! Pump RSP B to SG 2 Block Valve, AFB-UV-35

10. Pressurizet Backup Heaters Banks B10, B18, A05 Control Safety Injection Tank 2A RSP Vent Control SIB-HV-613

12. Safety Injection Tank 2B RSP Vent Control SIB-HV-623

13. Safety Injection Tank 1A RSP Vent Control SIB-HV-633

14. Safety Injection Tank 1B RSP Vent Control SIB-HV-643 C

15. Safety Injection Tank Vent RSP Val ves Power Supply SIB-HS-1

16. SG 1 line 2 Atmospheric Dump al ve Solenoid Air RSP Isolation Valves SGD-HY-178B and SGD-HY-178S

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

18. Control BLDG Battery Room D PHB"M3205 Essential Exhaust Fan BLDG Battery Room B

'HJB-J01A'ontrol

19. PHB-M3205 Es senti al Exhaus t Fan 'JB- J01B

20. Charger D Control 'attery PHB-M3209 AND PKD-H14 Room Circuits PKD-H14

21. ESF Switchgear Room PHB"M3205 Essential AHU HJB-Z03

22. LPSI Pump SIB-POl Breaker PBB-S04F Control

23. Diesel Generator B Breaker PBB-S04B Control

24. Essential Spray Pond Pump SPB-POl PBB-504C Breake. Control PALO VERDE " UNIT 1 3/4 3-50 AMENDMENT NO. 27

P 4*

4d C,

Cl C+

~O~TRCLbFP, PX U~<<

. REMOTE SHUTDOWN DISCONNECT SWITCHES SMITCH OIS CONNECT SMITCHES LOCATION SG 1 line 2 Atmospheric Dump Valve Solenoid Air RSP Isolation Valves SGB-HY-178A and SGB-HY-178R

2. SG 2- line 1 Atmospheric Dump Valve Solenoid Air RSP Isolation Valves SGB-HY;185A and SGB-HY-185R

3. Auxiliary Spray Valve RSP CHB-HV-203

4. Letdown to Regenerative RSP Heat Exchanger Isolation, CHB-UV-515

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

6. Auxiliary Feedwater Pump RSP B to SG 1 Control Valve, AFB-HV-30

7. Auxiliary Feedwater Pump RSP B to SG 2 Control Valve, Feedwater AFB-HV-31'uxiliary Pump RSP B to SG "1 Block. Valve, AFB-UV-34

9. Auxiliary Feedwater Pump 'SP B to SG 2 Block Valve, AFB-UV-35

10. Pressurizer Backup Heaters Banks RSP 83,0, B18, A05 Control, Safety Injection Tank'2A RSP Vent Control SIB-HV-613

. 12 Safety Injection Tank Vent Control SIB-HV-623 2B- 'RSP

13. Safety Injection Tank 1A RSP Vent Control SIB-HV-633

14. Safety Injection Tank 1B RSP Vent Control SIB-HV-643

15. Safety Injection Tank Vent RSP Valves Power Supply SIB-HS-. 1 A 16 SG 1 line 2 Atmospheric. Dump Valve Solenoid Air RSP Isolation Valves SGD-HY-178B and SGO-HY-178S

17. SG 2 line 1 Atmospheric Dump Valve Solenoid Air RSP Isolation Valves SGO-HY-185B and SGO-HY-185S 18 Control BLDG Battery Room D PHB-M3205 Essential Exhaust Fan 'HJB-J01A'ontrol

19. BLDG Battery Room B PHB-M3205 Essential Exhaust Fan 'HJB-JOZB'attery

20. Charger 0 Control PHB-M3209 AND PKD-H14 Room Circuits PKO-H14

21. ESF Switchgear Room PHB-M3205 Essential AHU HJB-Z03

22. ,LPSI Pump SIB-P01 Breaker PBB-504F Control

23. Diesel Generator B Breaker PBB-S04B Control 24 Essential Spray Pond Pump SPB-POl PBB-S04C Breaker Control PALO VERDE - UNIT 2 3/4 3-50

0 l'

j 2

0 u'Q

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

l. SG 1 line 2 Atmospheric Dump Valve Solenoid Air RSP Isolation Valves SGB-HY-178A and SGB-HY-178R

2. SG 2 line 1 Atmospheric Dump Valve Solenoid Air RSP Isolation Valves SGB-HY-185A and SGB-HY-185R

3. Auxiliary Spray Valve RSP CHB-HV-203

4. Letdown to Regenerative RSP

'Heat Exchanger Isolation, CHB-UV-515

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

6. Auxiliary Feedwater Pump RSP B to SG 1 Control Valve, AFB-HV-30

7. Auxiliary Feedwater Pump RSP 8 to SG 2 Control Valve, AFB-HV"31 'SP

8. Auxiliary Feedwater Pump B to SG 1 Block Valve, AFB-UV-34

9. Auxiliary Feedwater Pump RSP B to SG 2 Block Valve, AFB-UV-35

10. Pressurizer Backup Heaters Banks RSP e 11.

12.

B10, B18, A05 Control Safety Injection Tank 2A Vent Control SIB-HV-613 Safety Injection Tank 2B Vent Control SIB-HV-623 RSP RSP

13. Safety Injection Tank lA RSP Vent Cont'rol SIB-HV-633

14. Safety Injection Tank 1B RSP Vent Control SIB-HV-643

15. Safety Injection Tank Vent RSP Valves Power Supply SIB-HS-1 A

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

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

18. Control

'HJB-J01A'HB-M3205 BLDG Battery Room Essential Exhaust Fan D

19. Control BLDG Battery Room B PHB"M3205 Essential Exhaust Fan 'HJB-J01B'attery

20. Charger D Control PHB-M3209 AND PKD"H14 Room C i rcui ts PKD-H14

21. ESF Switchgear Room PHB-M3205 Essential AHU HJB-Z03

22. LPSI Pump SIB-P01 Breaker PBB"504F Control

23. Diesel Generator B Breaker PBB-5048 Control Essential Spray Pond Pump SPB-P01 PBB"504C Breaker Control PALO VERDE - UNIT 3 3/4 3"50

0 19

CGNTRGLLED BY USER TABLE 3.3-9B (continued)

REMOTE SHUTDOWN DISCONNECT SWITCHES SWITCH DISCONNECT SWITCHES LOCATION

50. LPSI-SD HX "B" Bypass PHB-M3803 S IB"HY-307

51. LPSI Pump "B" Recirc PHB-M3611 SIB-UY"668

52. LPSI Pump "B" Suction PHB"M3805 from RWT SIB-HV-692

53. SD Cooling LPSI Pump "B" PHB-M3611 Suction SIB-UV-652

54. SD Cooling LPSI Pump "B" PKD-B44 Suction SIB-UV-654 F

55. LPSI Header "B" to RC Loop PHB-M3611 2A SIB-UV-615

56. LPSI Header "8" to RC Loop PHB-M3640 28 SIB-UY"625 5?. VCT Outlet Isolation NHN-M7208 CHN- UV"501

58. RWT Gravity Feed gY NHN-M7209 CHN-HV-536

59. Shutdown Coo g Temperature PHB-M3416 Control SIB UY 658

60. Shutdown Coo >ng Heat Exchanger P HB" M3416 Bypass Valve SIB-HV-693

61. '4.16 KV Bus PBB-504 PBB-S04K Feeder from XFMR NBN"X04

62. 4. 16 KV Bus PBB"S04 PBB-S04L Feeder from XFMR NBN-X03

63. Electrical Penetration Room B PHB"M3640 ACU HAB"Z06

64. Control Room HVAC Isolation Dampers RSP HJ B-M01/H J 8 "M55

65. O.S.A. Supply Damper HJB-M02 RSP

66. O.S.A. Supply Damper HJB-M03 RSP

67. R.C.S. Sample Isolation Valve SSA-UV-203 SSA"J04

68. R.C.S. Sample Isolation Valve SSB-UV-200 RSP

69. 125 VDC Battery A Breaker P KA"M4101 Control Room Circuits PALO VERDE - UNIT 1 3/4 3"52 AMENDMENT NO. 27

t

\~

I+

% t 4

CGMTRQI.LED BY USER a

REMOTE SHUTDOWN DISCONNECT SWITCHES SMITCH DISCONNECT SWITCHES LOCATION SD HX "8" .to RC Loops PHB" M3416 49.'0.

2A/28 .SIB-HV-696 LPSI'-SD HX "8" Bypass PHB"M3803 SIB-HV-307

51. LPSI Pump "8" Recirc PHB" M3611 SIB-UY-668

52. LPSI Pump "8" Suction PHB-M3805 from RMT SIB-HY-692

'3. SD Cooling LPSI= Pump "8" PHB-M3611 Suction SIB-UV-652

54. SD Cooling LPSI Pump "8" PKD-844 Suction SID-UV-654

55. LPSI Header "8" to RC Loop PHB-M3611-2A SIB-UV-615

56. LPSI Header "8" to RC Loop PHB"M3640 28 SIB-UV-625

57. VCT Outlet Isolation NHN"M7208

'HN-UV-501

58. RWT Gravity Feed NHN-M7209 CHE-HY-536

~

59. Shutdown Cool g Temperature PHB" M3416 Control SIB V 658.

60. Shutdown Coo ing Heat Exchanger PHB-M3416 Bypass Valve SIB-HV-693

61. 4.16 KV Bus PBB-S04'eeder PBB-S04K from XFMR NBN-X04 e 62 4'.16 KY Bus PBB-S04 PBB-S04L Feeder from XFMR NBN-X03

63. Electrical Penetration Room 8 PHB-M3640 ACU HAB-106

64. Control Room HVAC Isolation Dampers RSP H JB-M01/H JB-M55

65. O.S.A. Supply Damper HJB-M02 RSP

'6. O.S.A. Supply Damper HJB-M03 RSP

67. R. C. S. Sample Isolation Val ve SSA-UV-203 SSA-J04

68. R.C.S. Sample Isolation Yalve SSB-UV-200 RSP 69 125. VDC Battery A Breaker

~ PKA-M4101 Control Room Circuits PALO VERDE - UNIT 2 3/4 3-52 CO~TROLLED BY USER

g~

N 0

TABLE 3.3-98 (Continued)

REMOTE SHUTDOWN DISCONNECT SWITCHES SWITCH DISCONNECT SWITCHES LOCATION

49. SD HX "B" to RC Loops PHB-M3416 2A/2B SIB-HV-696

50. LPSI-SD HX "B" Bypass PHB"M3803 SIB-HV"307

51. LPSI Pump "B" Recirc PHB-M3611 SIB-UV-668

52. LPSI Pump "B" Suction PHB-M3805 from RWT SIB-HV-692

53. SD Cooling LPSI Pump "B" PHB "M3611 Suction SIB-UV-652

54. SD Cooling LPSI Pump "B". PKD-B44 Suction SID-UV-654 55 LPSI Header "B" to RC Loop

~ PHB-M3611 2A SIB"UV"615

56. LPSI Header "B" to RC Loop PHB-M3640 2B SIB"UV"625

57. YCT Outlet Isolation NHN-M7208 CHN-UV-501

58. RWT Gravity Feed NHN-M7209 59.

CHE-HV-536 Shutdown Coo '.

Control SIB UV 658 Temperature PHB-M3416

60. Shutdown Coo ing Heat Exchanger PHB-M3416 Bypass Valve SIB-HV-693

61. 4. 16 KV Bus PBB-S04 PBB-S04K Feeder from XFMR NBN-X04

62. 4.16 KV Bus PBB-S04 PBB-S04L Feeder from XFMR NBN-X03

63. Electrical Penetration Room B PHB-M3640 ACU HAB-Z06

64. Control Room HVAC Isolation Dampers RSP H JB."M01/HJB-M55

65. O.S.A. Supply Damper HJB-M02 RSP

66. 0 S.A. Supply Damper HJB-M03

~ RSP

67. R. C. S. Sample Isol ation Val ve SSA-UV-203 SSA-J04

68. R.C.S. Sample Isolation Valve SSB-UV-200 RSP

69. 125 VDC Battery A Breaker PKA-M4101 Control Room Circuits PALO VERDE - UNIT 3 3/4 3-52

n CONTROLLED BY USER TABLE 3.3-9C (continued)

REMOTE SHUTDOWN CONTROL CIRCUITS SMITCH CONTROL CIRCUITS LOCATION

27. E"PGB"L36 480Y PGB"L3681 Supply Breaker to Load Center PGB-L36

28. Battery Charger PKB-H12 PHB"M3627 Supply Breaker

29. Battery Charger PKD-H14 PHB-M3209 Supply Breaker

30. Backup Battery Charger PHB"M3425 PKB-H16 Supply Breaker

31. Essential Spray Pond Pump PBB-S04C SPB-P01 32 ~ Essential Cooling Mater Pump PBB-S04M EMB-POl

33. Essential Chilled Mater PBB-S04G Chiller ECB-E01

34. Battery Room D Essential PHB"M3206 Exhaust Fan HJB-J01A

35. Battery Room 8 Essential PHB-M3207 Exhaust Fan HJB-J018

36. ESF Switchgear Room 8 PHB-M3203 Essential AHU HJB"E03

37. Electrical Penetration Room 8 PHB-M3631 ACU Fan HAB-E06

38. SIT Vent Valves Power RSP Supply SIB-HS-1 A

39. SIT 2A Vent Valve RSP 5 I 8" HV-613

40. SIT 28 Yent Valve RSP SIB-HY"623

41. SIT 1A Vent Valve RSP SIB" HV-633

42. SIT 18 Yent Yalve RSP S I 8-HV-643

43. LPSI Pump 8 PBB"504F SIB-POl

44. Containment Spray Pump 8 PHB"M3804 Discharger to SD HX "8" Valve SIB-HV-689

45. LPSI Containment Spray from PHB-M3810 SD HX "8" X-tie Yalve SIB-HY-695

46. Shutdown Cooling LPSI Suction PHB"M3605, Yalve SIB-HV-656

47. Shutdown Cooling Marmup Bypass PHB"M3806 Valve SIB-UV-690

48. LPSI Containment Spray to PHB-M3414 SD HX "8" X-tie Valve SIB-HV-694 PALO YERDE - UNIT 1 3/4 3" 54 AMENDMENT NO 27

-d 41

CQMTRQLLEP BY USER REMOTE SHUTDOWN CONTROL CIRCUITS SWITCH CONTROL CIRCUITS LOCATION

25. E-PGB L32B2 480V Main Supply Breaker PGB- L32B1 To Load'enter PGB-L32

26. E-PGB-L34B2 480V Main Supply Breaker PGB- L34B1 To Load Center PGB-L34

27. E-PGB-L36 480V PGB-L36B1 Supply Breaker To Load Center PGB-L36

28. Battery Charger PKB-H12 PHB-M3627 Supply Breaker

29. Battery Charger PKD-H14 PHB-M3209 Supply Breaker.

30. Backup Battery Charger PHB-M3425 PKB-H16 Supply Breaker 31 Essential Spray Pond Pump PBB-S04C SPB-P01

32. Essential Cooling Water Pump PBB-S04M EWB-P01

33. Essential Chilled Water PBB-S04G Chiller ECB-E01

34. Battery Room D Essential 'HB-M3206 Exhaust Fan HJB-JOlA

35. Battery Room B Essential PHB-M3207 Exhaust Fan HJB-J01B 36 ESF Switchgear Room B PHB-M3203 Essential AHU HJB-Z03

37. Electrical Penetration Room B PHB-M3631 ACU Fan HAB-Z06

38. SIT Vent Valves ower RSP Supply SIB-HS-1 A

39. SIT 2A Vent Valve 8

RSP SIB-HV-613

40. SIT 2B Vent'alve RSP SIB-HV-623

41. SIT 1A Vent Valve RSP SIB-HV-633 42 SIT 1B Vent Valve

~

RSP SIB-HV-643 43 LPSI Pump B PBB-S04F SIB-P01

44. Containment Spray Pump B PHB-M3804 Discharger to SD HX "B" Valve SIB-HV-689

45. LPSI Containment Spray from PHB-M3810 SD HX "B" X-tie Valve SIB-HV-695

46. Shutdown Cooling LPSI Suction PHB-M3605 Valve SIB-UV-656

47. Shutdown Cooling Warmup Bypass PHB-M3806 Valve SIB-HV-'690

48. LPSI Containment Spray to PHB-M3414 SD HX "B" X-tie Valve SIB-HV-694 PALO VERDE - UNIT 2 3/4 3-54 CC WT@GLLEB BY USE~

0 I

CONTROLLED BY USER TABLE 3.3-9C (Continued)

REMOTE SHUTDOWN CONTROL CIRCUITS SWITCH CONTROL CIRCUITS LOCATION 25 ~ E-PGB L32B2 480V Main Supply Breaker PGB-L32B1 To Load Center PGB-L32

26. E-PGB-L34B2 480V Main Supply Breaker PGB" L3481 To Load Center PGB-L34

27. E-PGB-L36 480V PGB-L36B1 Supply Breaker To Load Center PGB-L36

28. Battery Charger PKB-H12 PHB-M3627

,Supply Breaker

29. Battery Charger PKD-H14 PHB-M3209 Supply Breaker

30. Backup Battery Charger PHB-M3425 PKB-H16 .Supply Breaker

31. Essential Spray Pond Pump PBB-S04C SPB-Pol

32. Essential Cooling Mater Pump PBB-S04M EWB" P01

33. Essential Chilled Mater PBB-S04G Chiller ECB-EOl

34. Battery Room D Essential PHB-M3206 Exhaust Fan HJB-JOlA

35. Battery Room B Essential PHB"M3207 Exhaust Fan HJB-J01B

36. ESF Switchgear Room B PHB"M3203 Essential AHU HJB-Z03

37. Electrical Penetration Room B PHB-M3631 ACU Fan HAB-Z06

39. SIT Vent Valves Power RSP Supply SIB-HS-I A

39. SIT 2A Vent Valve RSP SIB-HV-613

40. SIT 2B Vent Valve RSP SIB-HV"623

41. SIT 1A Vent Valve RSP SIB-HV-633

42. SIT 1B Vent Valve RSP 5 I B-HV-643

43. LPSI Pump 8 PBB-504F S IB-P01

44. Containment Spray Pump B PHB-M3804 Discharger to SD HX "B" Valve SIB-HV-689

45. LPSI Containment Spray from PHB-M3810 SD HX "8" X-tie Valve SIB-HV-695

46. Shutdown Cooling LPSI Suction PHB-M3605 Valve SIB-UV-656

47. Shutdown Cooling Warmup Bypass PHB-M3806 Val ve SIB-HV-690

48. LPSI Containment Spray to PHB-M3414 SD HX "B" X-tie Valve SIB-HV-694 PALO VERDE - UNIT 3 3/4 3-54

4I>>-

tF l4

TABLE 3.3-9C (continued)

REMOTE SHUTDOWN CONTROL CIRCUITS SWITCH CONTROL CIRCUITS LOCATION

27. E"PGB-L36 480V PGB-L36B1 Supply Breaker to Load Center PGB-L36

28. Battery Charger PKB-H12 PHB-M3627 Supply Breaker

29. Battery Charger PKO-H14 PHB"M3209 Supply Breaker

30. Backup Battery Charger PHB"M3425 PKB-H16 Supply Breaker

, 31., Essential Spray Pond -Pump PBB"'504C SPB-Pol

32. Essential Cooling Mater Pump PBB"S04M

'WB-P01

33. Essential Chilled Mater PBB"S04G Chiller ECB-E01

34. Battery Room D Essential PHB"M3206 Exhaust Fan HJB-J01A

35. Battery Room B Essential PHB-M3207 Exhaust Fan HJB-J01B

36. ESF Switchgear Room B PHB-M3203 Essential AHU HJB-Z03

37. Electrical Penetration Room B PHB" M3631 ACU Fan HAB-Z06

38. SIT Yent Yalves Power RSP Supply SIB-HS-18A

39. SIT 2A Yent Yalve RSP SIB-HV-613

40. SIT 2B Vent Valve RSP SIB "HV"623

41. SIT lA Vent Valve RSP S IB-HY-633

42. SIT 1B Vent Valve RSP SIB"HV"643

43. LPSI Pump B PBB"S04F SIB-P01

44. Containment Spray Pump 8 PHB"M3804 Discharger to SD HX "B" Yal ve SIB-HY-689 45 ~ LPSI Containment Spray from PHB" M3810 SO HX "B" X-tie Valve SIB-HV-695

46. Shutdown Co lin PSI Suction PHB"M3605 Valve SIB HV 656

47. Shutdown C ling Warmup Bypass PHB-M3806 Valve SIB 90

48. LPSI Containment Spray to PHB-M3414 SD HX "B" X-tie Valve SIB-HV-694 PALO VERDE - UNIT 1 3/4 3-54 AMENDMENT NO. 27

'k k ~

0

,I l

CONTROLLED BY USER TABLE 3.3-9C continued)

REMOTE SHUTOOWN CONTROL CIRCUITS SWITCH CONTROL CIRCUITS LOCATION

49. SD HX "8" to RC Loops PHB-M3415 2A/28 Yalve SIB-HV-696

50. LPSI SD HX "8" Bypass PHB-M3803 Valve SIB-HY-307

51. LPSI Pump 8 Recirc. PHB-M3609 Yalve SIB-UY 88

52. LPSI Pump 8 Suc ion PHB-.M3805 From RWT SIB-HY-692

53. RC Loop to Shutdown PHB"M3604 Cooling Valve SIB-UV-652

54. RC Loop to Shutdown PKD-844 Cooling Yalve SIB-UV-654

55. LPSI Header 8 to RC PHB-M3606 Loop 2A Valve SIB-UV-61S

56. LPSI Header 8 to RC PHB-M3621 Loop 28 Valve SIB-UV-625

57. SDC "8" Temperature Control Valve PHB" M3412 SIB-HV"658

58. Control Room Ventilation Isolation RSP Dampers HJB-M01/HJB-MS5

59. O.S.A. Supply Damper H JB-M02 RSP

60. O.S.A. Supply Damper HJB-M03 RSP

61. Diesel Generator "8" Emergency Start DGB-801

62. Normal Offsite Power Supply Breaker PBB"S04K

63. Alternate Offsite Power Supply Breaker PBB"S04L

64. Battery "8" Breaker PKB" M4201

65. Battery "D" Breaker PKD-M4401

66. RCS Sample Isolation Valve SSA-UV"203 SSA-J04

67. RCS Sample Isolation Valve SSB-UV-200 SSB"J04

68. Train "8" Pumps Combined Recirc to RWT Valve RSP SI 8-UV-659

69. Shutdown Cooling Heat Exchanger Bypass PHB"M3413 Val ve SIB-HV-693

70. Battery "A" Breaker P KA"M4101 PALO VERDE " UNIT 1 3/4 3-55 AMENDMENT NO. 27

~ E h

4 t

~4 gV, 4

FOR INFORMATION ONLY 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:

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 .

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

b. 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 s

3.4. 5. 2 Reactor Coolant System leakage shall be limited to:

a0 Ho PRESSURE BOUNDARY LEAKAGE,

b. 1 gpm UNIDENTIFIED LEAKAGE, C. 1 gpm total primary-to-secondary leakage through all steam generators, and 720 gallons per day through any one steam generator,

d. 10 gpm IDENTIFIED LEAKAGE from the Reactor Coolant System, and

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

~ ~

6 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 wi thin 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' heal f ~!

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. 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.

C. 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:

INOPERABLE, 'I

a. With only one of the above required reactor coolant system vent paths 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 INFORMATION ONLY 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 INFORMATION ONLY EMERGENCY CORE COOLING SYSTEHS SURVEILLANCE RE UIREHENTS (Continued 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.

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

3. 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:

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

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

a. High pressure safety injection pump.* I

b. Low pressure safety injection pump.* I

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:

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 0

1

FOR INFORMATlON ONLY 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 Each containment spray system shall be demonstrated OPERABLE:

a ~ 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.

b. 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.

Co 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).

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

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

2. 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 INFORMATION ONLY t

CONTA[NtlENT SYSTEMS SURVE1LLANCE REQU1REHENTS Continued)

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

'e. 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 INFORMATION ONLY CONTAINHENT SYSTEHS SURVEILLANCE REQUIREHENTS (Continued)

d. At least once per 18 months, during shutdown, by Verifying 'that each automatic valve in the flow path actuates to its correct position on a containment spray actuation (CSAS) test signal,* and

2. 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.

Deferred until c cle 3 refuelin a PALO VERDE - UNI T 2 3/4 6-18 AHENDHENT NO. 30

CQINITIRQILILED BY USEIR TABLE 3. 6-1 (Continued)

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

D. CHECK VALVES (Continued)

CHE-V M70 41 Regenerative heat exchanger ora to RC loop 2A IAE-V 072 59 Containment service air utility N. A.

station .

SIB-V 533 67 Long term recirculation loop 2 CHE-V 835 72 RC pump seal injection water to N. A.

RCP 1A, 1B, 2A, 2B AFE-V 079¹ 75 Steam generator 1 auxiliary N. A.

feedwater AFE-V 080¹ 76 Steam generator 2 auxi 1 i ary N. A.

feedwater SIA-V 523 77 Long term recirculation loop 1 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 MAXIMUM ACTUATION VALVE PENETRATION TIME NUMBER NuntBER FUNCTION (SECONDS)

G. REQUIRED OPEN DURING ACCIDENT CONDITIONS SID-UY 654 26 From shutdown cooling RC loop 2 H.A.

SIB-UV 656 26 From shutdown cooling RC .loop 2 N.A.

SIB-HV 690 26 From shutdow'n coolina RC loop 2 N.A.

SIC-UV 653 2/ From shutdown cooling RC loop 1 H.A.

SIA-UY 655 2/ From shutdown cooling RC loop 1 H.A.

SIA-HV 2/ From shuiaown cooling RC loop 1 691'CC-HV 076~ 328 Containment pressure monitor

.HPA-.HV.J307A . -Containment to -hydrogen,monitoJ .

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

HCA-HV 074~ 5~4 Containment pressure monitor HCB-HY 075" 55A Containment pressure monitor HCD-HV 0778 62A CB pressure monitor N.A.

SID-HV 331 67 Long-term recirculation. loop 2 N.A..

recalculation CHB-HV 255 72 RC pump seal injection water N.A.

to RCP lA, 1B 2A> ZB SIC-HV 321 77 Long-term

~i .. loop 1 SGA-UY 1344 2 Main steam to auxiliary feedwater N.A."

turbine PNot Type C tested.

CGINIYRGLLk I5Y 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.

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.

' - b. 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 INFORMATION ONLY 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

'l l 'l

FOR INFORMATION ONLY

'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 l N FORMATION ON LY 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. 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 ~~

3. 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 INFORMATION ONLY 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:

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.

2. 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.

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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

, 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.

~

~g

~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

CONTROLLED BY USER

~ ff ~~

a 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 Each shutdown cooling subsystem shall be demonstrated OPERABLE:

If

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 leos.

b. 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

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e CONTROLLED BY USER 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 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.

,0 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 C. Nith .both letdown cooIing subsystems inoperable and both reactor coolant loops inoperable, initiate action to restore the required subsystems 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

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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

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~ 4 P g<

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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~ Determined OPERABLE at least once per 7 days by verifying correct alignment indicating power availability :'reaker

b. 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) Manual 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.

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

I

~l I

0

FOR INFORMATiON ONLY 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 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:

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.

r 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) Manual 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.

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

Al A

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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 TEST BASIS by: 'TAGGERED

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. 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.

C. 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.

d. At least once per 18 months during shutdown by:

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

2. '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.**"*

3. Verifying that the automatic load sequencers are OPERABLE with the interval between each load block within + 1 second of its design interval.~**~

4, Simulating a loss of offsite power by itself, and:

a) Verifying deenergization of the emer ency 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 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 mentt 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-

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

"""IfSpecificationtest~8 invalidate the 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

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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) 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.****

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, 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) *** ****

+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.

- - - De erred until cyc e re ueling outa e.

ERDE - UNIT 2 /4 8-5 AHENDHENT NO. 30

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0

FOR INFORMATlON ONLY

. ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued

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

9. Verifying the diesel generator's capability to:

a) Synchronize with the offsite power source while the generator is loaded with its emergency l ds upon a simulated restoration of offsite power **".*

b) Transfer its loads to the offsite power urce, and ***

c) Proceed through its shutdown sequence.****

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 ***

e. 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 INFORMATION ONLY 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 wi ll 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.

FOB INFORMATION ONLY m aa 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

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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 eff 0.95 or less, or

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

APPLI CAB I LITY: 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 eff reduced to 1 ess than or equal to 0. 95 or the boron concentration is restored to g. eater than or equal to 2150 ppm, whichever is the more restri cti ve.

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

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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 performing a load test of at least 3590 pounds and demonstr t'n 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 load cut off when the refueling machine load exceeds 1556 (1727)" .pounds-automatic "For initial fuel load only.

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

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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.

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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

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CONTROLLED BY USER 3/4. 10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTOOMN MARGIN AND KH - CEA MORTH TESTS 1

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~ 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 required

'by Specification 3.1.1.2 are restored. 1

b. 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.

y 4~'imited to low power. PHYSICS TESTING at the 320'F plateau.

PALO VERDE - UNIT 1 3/4 10-1 AMEHDMEHT NO. 23

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

1 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. CEA position, Reactor Coolant System average temperature,

d. Fuel burnup based on gross thermal energy generation,

e. 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

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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 required 1

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.

( 4.10.1.1 RE UIREMEHTS 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 .

'URVEILLANCE 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.

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 AMEHDMEHT HO. 2

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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.

APP ABI TY NOBE-+ .

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

'ed'ately t trip e b. Wi 0 the r atio hip igur 3.4-2, eactor pen react oolant wi hin the region mmedia ly open ystem te bre kers.

erature of unacceptab te reactor a d e

rip pressu e opera bre on on 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.

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CGMTIRGILILEB BY 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

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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.

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SPECIAL TEST EXCEPTIONS 3/4. 10. 5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY 3.10.5 ficati s e minim 3.1.1.

temperat and 3.2.

e and presg, re for cd icality l may be suspended during low temp rature PHY CS

'ts of Sp i-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.

The r ctor trip tpoints o the OPER@ LE Variabl Overpower ip cha els are se at < 20K df RATED T fRMAL POWER and c ~ e Reactor oolant Sy tern tempe ature and ssure relati nship is maintaine ithin t 6 acceptab e region of p 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 hours pr or to ini iating low temperatu e PHYSICS T STS, ERM OWN".

PALO VERDE - UNIT 3 3/4 10"5

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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. Operations i volving a reducti n in boron c centration f the Reacto Coolant Sy em are suspended

b. 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

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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.

SURVEILLANCE RE UIREMENTS t

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

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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 be ow the m~nsmum crs >ca empera ure an pressure during PHYSICS TEST( Mich are required to verify the low temperature physics 1

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

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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 e ow t e m)nimum cri )ca tempera ure an pre sure during PHYSICS TESTF which are required to verify 1

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. Biological shielding survey test

2. Isothermal temperature coefficient tests

3. CEA group tests 4 Boron worth tests

5. 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 ffi ci ent.

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

OW eve s ws elow e msnsmum crs seal temperature and pressure 1

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. Biological shielding survey test

2. Isothermal temperature coefficient tests

3. CEA group tests Boron worth tests

5. Critical configuration boron concentration PALO YEROE - UNIT 3 8 3/4 10-1

ML17305B113

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