Text

Amend 2 to License NPF-74,revising Tech Specs Re Shutdown Margin Requirements
	ML20149D081
Person / Time
Site:	Palo Verde
Issue date:	01/26/1988
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20149D088	List: ML20149D081; ML20149D095;
References
	NUDOCS 8802090373
	Download: ML20149D081 (53)
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o UNITED STATES

',j NUCLEAR REGULATORY COMMISSION 3#

E WASHlfJGTON, D. C. 20555

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i ARIZONA PUBLIC SERVICE COMPANY, ET AL.

DOCKET N0. STN 50-530 PALO VERDE SUCLEAR GENERATING STATION, UNIT NO. 3 AM2NDMENT TO FACILITY OPERATING LICENSE Amendment No. 2.

License No. NPF-74 1.

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

A.

The application for amendment, dated January 23, 1987, as supplemented by letters dated April 23, June 8 and July 17, October 1, and November 10, 1987, by the Arizona Public Service Company (APS) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison Company, Public Service Company of New Mexico, Los Angeles Department of Water and Pcwer, and Southern California Public Power Authority (licensees), complies with the standards and requirements of the Atomic Energy act of 1954, as amended (the Act) and the Comission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in confomity with the application, the provisions of the Act, and the regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comen defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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8802090373 880126' PDR ADOCK 05000530 P

PDR I

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~ 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows:

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(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.

2, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of-the date of issuance. The changes in the Technical Specifications are to become effective within one week after initially reaching 100% power or within 30 day of issuance of the amendment, whichever is later.

In the period between issuance of the amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the time. The period of time during changeover shall be minimized.

FOR THE NUCLEAR REGULATORY COMMISSION 280 A ct Knighton,j' Director Georg Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

Changes to the Technice.1 Specifications Date of Issuance: January 26, 1988 l

l

January 26, 1988 ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 2 TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO. STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

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

Also to be replaced are the following overleaf pages to the amended pages, knendment Pages Overleaf Pages I

II III IV IX X

XIII XIV XX XIX 1-4 1-3 1-5 1-6 1-7 1-8 2-4 2-3 2-5 2-6 3/4 1-1 3/4 1-2 3/4 1-2a 3/4 1-3 3/4 1-4 3/4 1-8 3/4 1-7 3/4 1-9 3/4 1-10 3/4 1-13 3/4 1-14 3/4 1-16 3/4 1-15 3/4 1-17 3/4 1-18 3/4 1-19 3/4 1-20 3/4 1-21 3/4 1-22 3/4 3-5 3/4 3-6 3/4 10-1 3/4 10-2 3/4 10-9 B 3/4 1-1 B 3/4 1-la B 3/4 1-2 B 3/4 10-2 B 3/4 10-1

q INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 ACTI0N......................................................

1-1 1.2 AXIAL SHAPE INDEX...........................................

1-1

1. 3 AZIMUTHAL POWER TILT - T...................................

1-1 q

1.4 CHANN E L C A L I B RAT I O N.........................................

1-1

1. 5 CHANNEL CHECK...............................................

1-1 1.6 CHANNEL FUNCTIONAL TEST.....................................

1-2

1. 7 CONTAINMENT INTEGRITY..............;........................

1-2

1. 8 CONT RO L LED L EA KAG E..........................................

1-2 1.9 CORE ALTERATION.............................................

1-2 1.10 DOSE EQUIVALENT I-131........j..............................

1-3 1.11 E - AVERAGE DISINTEGRATION ENERGY...........................

1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME....................

1-3 1.13 FREQUENCY N0TATION..........................................

1-3 1.14 GASEOUS RADWASTE SYSTEM.....................................

1-3 1.15 IDENTIFIED LEAKAGE..........................................

1-3 1.16 KN-1**********************''''********'*

1-4 1.17 MEMBER (S) 0F THE PUBLIC.....................................

1-4 1.18 0FFSITE DOSE CALCULATION MANUAL (00CM)......................

1-4 1.19 O P E RAB LE - O P E RAB I LITY......................................

1-4 1.20 O P E RAT I O N A L MO D E - M0 D E..................................... 1-4 1.21 PHYSICS TESTS...............................................

1-4 1.22 PLANAR RADIAL PEAKING FACTOR - F 1~4 xy***

1.23 PRESSURE BOUNDARY LEAKAGE...................................

1-5 1.24 PROCESS CONTROL PROG RAM (PCP)...............................

1-5 1.25 PURGE - PURGING.............................................

1-5 1.26 RATED THERMAL'P0WER.........................................

1-5 1.27 REACTOR TRIP SYSTEM RESPONSE TIME...........................

1-5 1.28 REPORTABLE EVENT............................................

1-5 1.29 SHUTDOWN MARGIN.............................................

1-6 1.30 SITE B0VNDARY...............................................

1-6 PALO VERDE - UNIT 3 I

AMENDMENT NO. 2

INDEX DEFINITIONS i

SECTION PAGE 1.31 50FTWARE....................................................

1-6 1.32 SOLIDIFICATION..............................................

1-6 1.33 SOURCE CHECK................................................

1-6 1.34 STAGGERED TEST BASIS........................................

1-6 1.35 THERMAL P0WER...............................................

1-6 1.36 UNIDENTIFIED LEAKAGE........................................

1-7 1.37 UNRESTRICTED AREA...........................................

1-7 1.38 VENTILATION EXHAUST TREATMENT SYSTEM........................

1-7 1.39 VENTING.....................................................

1-7 i

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PALO VERDE - UNIT 3 II AMENDMENT NO. 2 1

i

l INDEX f

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE.............................................

2-1 2.1.1.1 0NBR.....................................................

2-1 2.1.1.2 PEAK LINEAR HEAT RATE....................................

2-1 2.1.2 REACTOR COO LANT SYSTEM PRESSURE..........................

2-1 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 R EACTO R TRI P SETP0INTS.....................................

2-2 f

i BASES w

SECTION PAGE 2.1 SAFETY LIMITS 2.1.1 REACTOR C0RE...............................................

B 2-1 2.1.2 REACTOR COOLANT SYSTEM PRESSURE............................

B 2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS 2.2.1 REACTOR TRIP SETP0INTS.....................................

B 2-2 PALO VERDE - UNIT 3 III

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j

SECTION PAGE 3/4.0 APPLICABILITY..............................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL SHUTDOWN MARGIN - ALL CEAs FULLY INSERTED.............

3/4 1-1 SHUTDOWN MARGIN - K ANY CEA WITHDRAWN............

3/4 1-2 N-1 MODERATOR TEMPERATURE C0 EFFICIENT.....................

3/4 1-4 MINIMUM TEMPERATURE FOR CRITI'CALITY...................

3/4 1-6 3/4.1.2 BORATION SYSTEMS FLOW PATHS - SHUTD0WN.................................

3/4 1-7 FLOW PATHS - 0PERATING................................

3/4 1-8 CHARGING PUMPS - SHUTD0WN.............................

3/4 1-9 CHARGING PUMPS - 0PERATING............................

3/4 1-10 l

BORATED WATER SOURCES - SHUTD0WN......................

3/4 1-11 BORATED WATER SOURCES - OPERATING.....................

3/4 1-13 BO RON D I LUT I O N A LARMS.................................

3/4 1-14 3/4.1.3 MOVABLE CONTROL ASSEMBLIES CEA P0SITION..........................................

3/4 1-21 POSITION INDICATOR CHANNELS - OPERATING...............

3/4 1-25 POSITION INDICATOR CHANNELS - SHUTDOWN................

3/4 1-26 CEA DROP TIME.........................................

3/4 1-27 SHUTDOWN CEA INSERTION LIMIT..........................

3/4 1-28 REGULATING CEA INSERTION LIMITS.......................

3/4 1-29 1

PALO VERDE - UNIT 3 IV AMENDMENT NO. 2 1

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE ELECTRICAL POWER SYSTEMS (Continued) 3/4.8.2 0.C. SOURCES 0PERATING............................................

3/4 8-9 SHUTD0WN.............................................

3/4 8-13 3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS 0PERATING............................................

3/4 8-14 i

SHUTD0WN.............................................

3/4 8-16 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE 0EVICES.................................

3/4 8-17 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES.

3/4 8-40 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.....................................

3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................

3/4 9-2 3/4.9.3 DECAY TIME..............................................

3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

3/4 9-4 3/4.9.5 COMMUNICATIONS..........................................

3/4 9-S 3/4.9.6 REFUELING MACHINE.......................................

3/4 9-6 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING.........

3/4 9-7 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL.....................................

3/4 9-8 LOW WATER LEVEL......................................

3/4 9-9 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................ 3/4 9-10 3/4.9.10 WATER LEVEL - REACTOR VESSEL FUEL ASSEMBLIES........................

3/4 9-11 CEAs...................................

3/4 9-12 l

3/4.9.11 WATER LEVEL - STORAGE P00L..............................

3/4 9-13 l

3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM..............

3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN AND K.y - CEA WORTHTESTS..............

3/4 10-1 g

3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS.............

3/4 10-2 3/4.10.3 REACTOR COOLANT L00PS...................................

3/4 10-3 PALO VERDE - UNIT 3 IX AMEN 0 MENT NO. 2

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.10.4 CEA POSITION, REGULATING 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 N-1 3/4.11 RADI0 ACTIVE EFFLUENTS C

3/4.11.1 SECONDARY SYSTEM LIQUID WASTE DISCHARGES TO ONSITE EVAPORATION PONDS CONCENTRATION...........................................

3/4 11-1 00SE....................I...............................

3/4 11-5 LIQUID HO LDUP TANKS.....................................

3/4 11-6 3/4.11.2 GASE0US EFFLUENTS DOSE RATE...............................................

3/4 11-7 DOSE - NOBLE GASES......................................

3/4 11-11 DOSE - 10 DINE-131, 10 DINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE F0RM.....................

3/4 11-12 GASE0US 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 RADI0 ACTIVE WASTE.................................

3/4 11-16 3/4.11.4 TOTAL 00SE..............................................

3/4 11-18 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 GRAM......................................

3/4 12-1 3/4.12.2 LAND USE CENSUS.........................................

3/4 12-11 3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM......................

3/4 12-12 j

i PALO VERDE - UNIT 3 X

AMENDMENT NO. 2

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE...........................................

B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.........

B 3/4 7-3 3/4.7.3 ESSENTIAL COOLING WATER SYSTEM..........................

B 3/4 7-3 3/4.7.4 ESSENTIAL SPRAY POND SYSTEM.............................

B 3/4 7-4 3/4.7.5 ULTIMATE HEAT SINK......................................

B 3/4 7-4 3/4 7.6 ESSENTIAL CHILLED WATER SYSTEM..........................

B 3/4 7-4 3/4.7.7 CONTROL ROOM ESSENTIAL FILTRATION SYSTEM................

B 3/4 7-5 3/4.7.8 ESF PUMP ROOM AIR EXHAUST. CLEANUP SYSTEM................

B 3/4 7-5 1

3/4.7.9 SNUBBERS................................................

B 3/4 7-5 3/4.7.10 SEALED SOURCE CONTAMINATION.............................

B 3/4 7-7 3/4.7.11 SHUTDOWN COOLING SYSTEM.................................

B 3/4 7-7 3/4.7.12 CONTROL ROOM AIR TEMPERATURE............................

B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and ONSITE POWER DISTRIBUTION SYSTEMS................

B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES.................

B 3/4 8-3 i

3/4.9 REFUELING OPERATIONS l

l 3/4.9.1 BORON CONCENTRATION.....................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION.........................................

B 3/4 9-1 3/4.9.3 DECAY TIME..............................................

B 3/4 9'-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS..........................................

B 3/4 9-1 3/4.9.6 REFUELING MACHINE.......................................

B 3/4 9-2 l

PALO VERDE - UNIT 3 XIII AMENDMENT NO. 2 s

- + =

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INDEX BASES SECTION PAGE 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING.........

B 3/4 9-2 3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION................

B 3/4 9-2 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM.............

B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE P0OL...........................................

B 3/4 9-3 3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM..............

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN AND K

- CEA FORTH TESTS..............

B 3/4 10-1 N-1 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS................

B 3/4 10-1 3/4.10.3 R E ACTO R COO LANT LOOP S... 7..............................

B 3/4 10-1 3/4.10.4 CEA POSITION, REGULATING CEA INSERTION LIMITS AND REACTOR COOLANT COLD LEG TEMPERATURE................

B 3/4'10-1 3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY........

B 3/4 10-1 3/4.10.6 SAFETY INJECTION TANKS..................................

B 3/4 10-2 3/4.10.7 SPENT FUEL POOL LEVEL...................................

B 3/4 10-2 3/4.10.8 SAFETY INJECTION TANK PRESSURE..........................

B 3/4 10-2 3/4.10.9 SHUTDOWN MARGIN AND K

- CEDMS TESTING................

B 3/4 10-2 N-1 3/4.11 RADI0 ACTIVE EFFLUENTS 1

3/4.11.1 SECONDARY SYSTEM LIQUID WASTE DISCHARGES TO ONSITE EVAPORATION P0NDS.......................................

B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS.......................................

B 3/4 11-2 3/4.11.3 SOLID RADI0 ACTIVE WASTE.................................

B 3/4 11-5 3/4.11.4 TOTAL 00SE..............................................

B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MO N I TO R I NG P R0G RAM......................................

B 3/4 12-1 3/4.12.2 LAND USE CENSUS.........................................

B 3/4 12-2 INTER'ABORATORY COMPARISON PR0 GRAM......................

B 3/4 12-2 3/4.12.3 L

i PALO VERDE - UNIT 3 XIV AMENDMENT NO. 2

INDEX LIST OF FIGURES PAGE 3.1-1A SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE............

3/4 1-2a 3.1-1 ALLOWABLE MTC MODES 1 AND 2.................

3/4 1-5 3.1-2 MINIMUM 80 RATED WATER V0LUMES..........................

3/4 1-12 3.1-2A PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER.......

3/4 1-23 3.1 2B CORE POWER LIMIT AFTER CEA DEVIATION...................

3/4 1-24 3.1-3 CEA INSERTION LIMITS VS THERMAL POWER (COLSS IN SERVICE).....................................

3/4 1-31 3.1-4 CEA INSERTION LIMITS VS THERMAL POWER (COLSS OUT OF SERVICE).................................

3/4 1-32 3.2-1 ONBR MARGIN OPERATING LIMIT BA' SED ON COLSS (COLSS IN SERVICE).....................................

3/4 2-6 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATOR (COLSS OUT 0F,. SERVICE)......................

3/4 2-7 3.2-3 REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POWER LEVEL..................................................

3/4 2-10 3.3-1 DNBR MARGIN OPERATING LIMIT BASED ON COLSS FOR BOTH CEAC'S IN0PERABLE.............................

3/4 3-10 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY C0OLANT SPECIFIC ACTIVITY

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

3/4 4-27 3.4-2 REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR 0 TO 10 YEARS OF FULL POW 0PERATION................................ER 3/4 4 29 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

3/4 7-26 B 3/4.4-1 NIL-DUCTILITY TRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E > 1 MeV) NEUTRON FLUENCE (550*F IRRADIATION)....................................

B 3/4 4-10 5.1-1 SITE AND EXCLUSION B0VNDARIES..........................

5-2 5.1-2 LOW POPUL'ATION20NE....................................

5-3 5.1-3 GASEOUS RELEASE P0INTS.................................

5-4 6.2-1 0FFSITE ORGANIZATION...................................

6-3 6.2-2 ONSITE UNIT ORGANIZATION...............................

6-4 PALO VERDE - UNIT 3 XIX AMENDMENT NO. 2

(

INDEX LIST OF TABLES PAGE 1.1 FREQUENCY N0TATION......................................

1-8

1. 2 OPERATIONAL M0 DES.......................................

1-9 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS..................................................

2-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL k., DES.....................

3.1-1 FOR K,ff > 0.98.........................................

3/4 1-16 3.1-2 FOR 0.98 > K,ff > 0.97..................................

3/4 1-17 3.1-3 FOR 0.97 > K,ff > 0.96..................................

3/4 1-18 3.1-4 FOR 0.96 > K,ff > 0.95..............

3/4 1-19 3.1-5 F O R K, f f <_ 0. 9 5.........................................

3/4 1-20 3.3-1 REACTOR PROTECTIVE INSTRUMENTATION......................

3/4 3-3 3.3-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.......

3/4 3-11 3.3-2a INCREASES IN BERRO, BERR2, AND BERR4 VERSUS RTD DELAY TIMES.............................................

3/4 3-13 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-14 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.........................................

3/4 3-18 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES.............................

3/4 3-25 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES...............,

3/4 3-28 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............

3/4 3-31 3.3-6 RADIATION MONITORING INSTRUMENTATION....................

3/4 3-38 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-40 3.3-7 SEISMIC HONITORING INSTRUMENTATION......................

3/4 3-43 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

3/4 3-44 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION...............

3/4 3-46 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................

3/4 3-47 3.3-9A REMOTE SHUTDOWN INSTRUMENTATION.........................

3/4 3-49 3.3-3B REMOTE SHUTDOWN DISCONNECT SWITCHES.....................

3/4 3-50 i

PALO VERDE - UNIT 3 XX l

DEFINITIONS

('

DOSE EQUIVALENT I-131 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/

gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134 and I-135 actually present.

The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, "Calculation of Distance Factors for Power and Test Reactor Sites."

E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

ENGINEERED SAFETY FEATURES RESPONSE TIME.

1.12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation 7,etpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).

Times shall include diesel generator starting and sequence loading delays where e.pplicable.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

GASEOUS RADWASTE SYSTEM 1.14 A GASEOUS RADWASTE SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for tne purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:

l l

Leakage into closed systems, other than reactor coolant pump a.

controlled bleed-off flow, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or b.

Leakage into the containment atmosphere from sources that are both, specifically located and known either not to interfere with the operation'of leakage detection systems or not to be PRESSURE l

BOUNDARY LEAKAGE, or c.

Reactor Coolant System leakage through a steam generator to the secondary system.

PALO VERDE - UNIT 3 1-3

i DEFINITIONS l

KN-1 1.16 K is the k effective calculated by considering the actual CEA configura-N-1 tion and assuming that the fully or partially inserted full-length CEA of the highest inserted worth is fully withdrawn.

MEMBER (S) 0F THE PUBLIC 1.17 MEMBER (S) 0F THE PUBLIC shall include all persons who are not l

occupationally associated with the plant.

This category does not include employees of the licensee, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the

plant, f

OFFSITE DOSE CALCULATION MANUAL (00CM) 1.18 The OFFSITE 00SE CALCULATION MANUAL shall contain the current methodology

{;

and parameters used in the calculation of offsite doses due to radioactive gaseous and liquid effluents, in thie calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the environmental radiological monitoring program.

OPERABLE - OPERABILITY 1.19 A system, subsystem, train, component, or device shall be OPERABLE or l

have OPERABILITY when it is capable of performing its specified function (s),

and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).

OPERATIONAL MODE - MODE 1

1.20 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and cold leg reactor jl coolant temperature specified in Table 1.2.

PHYSICS TESTS 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental ll nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14.0 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or'(3) otherwise approved by the Commission.

PLANAR RADIAL PEAKING FACTOR - Fy 1.22 The PLANAR RADIAL PEAKING FACTOR is the ratio of the peak to plane I

average power density of the individual fuel rods in a given horizontal plane, excluding the effects of azimuthal tilt.

)

PALO VERDE - UNIT 3 1-4 AMENOMENT NO. 2 l

4

I DEFINITIONS I

i l

PRESSURE BOUNDARY LEAKAGE 1.23 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube l

leakage) through a nonisolable fault in a Reactor Coolant System component body, pipe wall, or vessel wall.

PROCESS CONTROL PROGRAM (PCP) 1.24 The PROCESS CONTROL PROGRAM shall contain the provisions to assure that I

the SOLIDIFICATION of wet radioactive wastes results in a waste form with properties that meet the requirements of 10 CFR Part 61 and of low level radioactive waste disposal sites.

The PCP shall identify process parameters influencing SOLIDIFICATION such as pH, oil content, H O content, solids content, 2

ratia of solidificatian agent to waste and/or necessary additives for each type of anticipated waste, and the acceptable boundary conditions for the process parameters shall be identified for each waste type, based on laboratory scale and full-scale testing or experience.

The PCP shall also include an identification of conditions that must be' satisfied, based on full-scale testing, to assure that dewatering of bead resins, powdered resins, and filter sludges will result in volumes of free water, at the time of disposal, within the limits of 10 CFR Part 61 and of. low level radioactive waste disposal sites.

PURGE - PURGING 1.25 PURGE or PURGING shall be the controlled process of discharging air or l

gas from a confinement to maintain temperature, pressure, humidity, concentra-tion, or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

RATED THERMAL POWER 1.26 RATED THERMAL POWER shall be a total reactor core heat transfer rate to l

the reactor coolant of 3800 MWt.

REACTOR TRIP SYSTEM RESPONSE TIME 1.27 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from l

when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

REPORTABLE EVENT 1.28 A REPORTABLE EVENT shall be any of those conditions specified in l

Sections 50.72 and 50.73 to 10 CFR Part 50.

l PALO VERDE - UNIT 3 1-5 AMENDMENT NO. 2

DEFINITIONS SHUTOOWN MARGIN 1.29 SHUTOOWN MARGIN shall be the instantaneous amount of reactivity by which I

the reactor is subcritical or would be subcritical from its present condition assuming:

a.

No change in part-length control element assembly position, and b.

All full-length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.

SITE BOUNDARY 1.30 The SITE BOUNDARY shall be that line beyond which the land is neither l

owned, nor leased, nor otherwise controlled by the licensee.

SOFTWARE 1.31 The digital computer SOFTWARE for the' reactor protection system shall be l

the program codes including their associated data, documentation, and procedures.

SOLIDIFICATION 1.32 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid l

systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

SOURCE CHECK 4

1.33 A SOURCE CHECK shall be the qualitative assessment of channel response l

when the channel sensor is exposed to a source of increased radioactivity.

]

STAGGERED TEST BASIS 1.34 A STAGGERED TEST BASIS shall consist of:

l a.

A test schedule for n systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into n equal subintervals, and b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER 1.35 THERMAL POWER shall be the total reactor core heat transfer rate to the

{

l reactor coolant.

PALO VERDE - UNIT 3 1-6 AMEN 0 MENT NO. 2

DEFINITIONS UNIDENTIFIED LEAKAGE 1.36 UNIDENTIFIED LEAKAGE shall be all leakage which does not constitute l

either IDENTIFIED LEAKAGE or reactor coolant pump controlled bleed-off flow.

UNRESTRICTED AREA 1.37 An UNRESTRICTED AREA shall be any area at or beyond the SITE B0UNDARY l

access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE B0UNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.38 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and I

installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilation or. vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing fodines or partic-ulates from the gaseous exhaust stream prior to the release to the environment.

Such a system is not considered to have any effect on noble gas effluents.

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.39 VENTING shall be the controlled process of discharging air or gas from a l

confinement to maintain temperature, pressure, humidity, concentration, or otner operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

1 PALO VERDE - UNIT 3 1-7 AMENDMENT NO. 2

TABLE 1.1 FREQUENCY NOTATION NOTATION FREQUEQ S

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

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

4/M At least 4 times per month at intervals no greater than 9 days and a minimum of 48 times per year.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 184 days.

R At liast once per 18 months.

P Completed prior to each release.

S/U Prior to each reactor startup.

W N.A.

Not applicabis.

l t

PAL 0 VERDE - UNIT 3 1-8

q

~

i TABLE 2.2-1 l

I REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS i

FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES 7

I.

TRIP GENERATION g

A.

Process i

1.

Pressurizer Pressure - High

$ 2383 psia 5 2388 psia l

2.

Pressurizer Pressure - Low 1 1837 psia (2) 1 1822 psia (2) 3.

Steam Generator Level - Low 1 44.2% (4) 1 43.7% (4) 4.

Steam Generator Level - High

< 91.0% (9)

< 91.5% (9) 9

]

5.

Steam Generator Pressure - Low 1 919 psia (3) 1 912 psia (3) 6.

Containment Pressure - High

$ 3.0 psig

< 3.2 psig 7.

Reactor Coolant Flow - Low a.

Rate 5 0.115 psi /sec (6)(7)

< 0.118 psi /sec (6)(7) i b.

Floor 1 11.9 psid(6)(7) 1 11.7 psid (6)(7) i c.

Band

< 10.0 psid(6)(7)

< 10.2 psid (6)(7) l i

8.

Local Power Density - High

< 21.0 kW/ft (5)

$ 21.0 kW/ft (5) 9.

DNBR - Low 1 1.231 (5) 1 1.231 (5) i i

8.

Excore Neutron Flux l

1.

Variable Overpower Trip a.

Rate

< 10.6%/ min of RATED

< 11.0%/ min of RATED i

THERMAL POWER (8)

THERMAL POWER'(8) b.

Celling

< 110.0% of RATED

< 111.0% of RATED THERMAL POWER (8)

THERMAL POWER (8) c.

Band

< 9.8% of RATED

< 10.0% of RATED THERMAL POWER (S)

THERMAL POWER (8) 1 I

TABLE 2.2-1 (Continued)

Ig REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS

5i FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES

[

2.

Logarithmic Power Level - High (1) a.

Startup and Operating

< 0.010% of RATED

< 0.011% of RATED l

h THERMAL POWER THERMAL POWER b.

Shutdown

< 0.010% of RATED

< 0.011% of RATED THERMAL POWER THERMAL POWER C.

Core Protection Calculator System 1.

CEA Calculators Not Applicable Not Applicable 2.

Core Protection Calculators Not Applicable Not Applicable D.

Supplementary Protection System Pressurizer Pressure - High

< 2409 psia

< 2414 psia II.

RPS LOGIC A.

Matrix Logic Not Applicable Not Applicable B.

Initiation Logic Not Applicable Not Applicable III. RPS ACTUATION DEVICES A.

Reactor Trip Breakers Not Applicable Not Applicable B.

Manual Trip Not Applicable Not Applicable 29

-4 5

TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATIONS (1) Trip may be manually bypassed above 10 4% of RATED THEPJ4AL POWER; bypass shall be automatically removed when THERM,a. POWER is less than or equal to 10 4% of RATED THERMAL POWER.

(2)

In MODES 3-4, value may be decreased manually, to a minimum of 100 osia, as pressurizer pressure is reduced, ;/ovided the margin between the pres-surizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is incre sed antil the trip setpoint is reached.

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

(3)

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

(4) % of the distance betwaen steam generator upper and lower level wide range instrument nozzles.

(5) As stored within the Core Protection Calculator (CPC).

Calculation of the trip setpoint includes measurement, calculktional and processor uncer-tainties, and dynamic allowances.

Trip may be manually bypassed below 10 4%

l of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 10 4% of RATED THERMAL POWER.

l The approved DNBR limit is 1.231 which includes a partial rod bow penalty compensation.

If the fuel burnup exceeds that for which an increased rod bow penalty is required, the DNBR limit shall be adjusted.

In this case a DNBR trip setpoint of 1.231 is allowed provided that the difference is com-pensated by an increase in the CPC addressable constant BERR1 as follows:

RB - RB BERRi

= BERRi Il +

~100 d

)

3 new old where BERR1 is the uncompensated value of BERR1; RB is the fuel rod old bow penalty in % DNBR; RB, is the fuel rod bow penalty in % DNBR already accounted for in the DNBR limit; POL is the power operating limit; and' d (% POL)/d (% DNBR) is the absolute value of the most adverse derivative of POL with respect to DNBR.

PALO VERDE - UNIT 3 2-5 AMENDMENT NO. 2

{

^

I TABLE 2.2-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS TABLE NOTATIONS (Continued) l (6) RATE is the maximum rate of decrease of the trip setpoint.

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

j l

FLOOR is the minimum value of the trip setpoint.

IIE3~is the amount by which the, trip setpoint is below the input signal l

unless limited by Rate or Floor.

Setpoints are based on steam generator differential pressure.

(7) TheIsetpointmaybealteredtodisabletripfunctionduringtesting pursuant to Specification 3.10.3.

i (8) RATE is the maximum rate of increase of the trip setpoint.

(The rate at

,wnich the setpoint can decrease is no slower than five percent per second.)

CEILING is the maximum value of the. trip setpoint.

EASD is the amount by which the trip setpoint is above the steady state input signal unless limited by the rate or the ceiling.

e (9) % of the distance between, steam generator upper and lower level narrow range instrument nozzles.

j, I

I AMDOTNT WD.1

)

PALO VERDE - LaGT 3

.b6 u

REACTIVITY CONTROL SYSTEMS 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - ALL CEAs FULLY INSERTED l

LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.0%

l delta k/k.

APPLICABILITY:

MODES 3, 4*, and 5* with all full-length CEAs fully inserted.

l ACTION:

With the SHUTDOWN MARGIN less than 1.0% delta k/k, immediately initiate and l

continue boration at greater than or equal to 26 gpm to reactor coolant system of a solution containing greater than or equal to 4000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.0% delta k/k at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of at least the following factors:

1.

Reactor Coolant System boron concentration, 2.

CEA position, 3.

Reactor Coolant System average temperature, i

4.

Fuel burnup based on gross thermal energy generation, 5.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within + 1.0% delta k/k at least once per 31 Effective Full Power Days (EFPD).

Tiiis comparison shall consider at least those factors stated in Specification 4.1.1.1.1, above.

The predicted l

reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each fuel.

loading.

See Special Test Exception 3.10.9.

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

O REACTIVITY CONTROL SYSTEMS SHUTOOWN MARGIN - K,1 - ANY CEA WITHDRAWN g

LIMITING CONDITION FOR OPERATION 3.1.1. 2 a.

The SHUTDOWN MARGIN shall be greater than or equal to that shown in Figure 3.1-1A, and b.

For T less than or equal to 500'F, K shall be less than 0.99.

l cold N-1 APPLICABILITY:

MODES 1, 2*, 3*, 4*, and 5* with any full-length CEA fully or partially withdrawn.

ACTION:

a.

With the SHUTDOWN MARGIN less than that in Figure 3.1-1A, immediately initiate and continue boration at greater than or equal to 26 gpm to the reactor coolant system of a solution containing greater than or equal to 4000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored, and i b.

With T less than or equal to 500*F and 7 greater than or equal cold to 0.99, immediately vary CEA positions and/or initiate and continue boration at greater than or equal to 26 gpm to the reactor coolant system of a solution containing greater than or equal to 4000 ppm boron or equivalent until the required K -1 is restored.

N SURVEILLANCE REQUIREMENTS 4.1.1.2.1 With any full-length CEA fully or partially withdrawn, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that in Figure 3.1.1A:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the CEA(s) is inoperable.

If the inoperable CEA is immovable as a result of excessive friction or mechanical interference or known to be untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s).

See Special Test Exceptions 3.10.1 and 3.10.9.

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

I 7.

i I

).............j..............:............. y.....,...... p..).'

...... p............. j:

i-i i

(500,6.0) i 6'

i i

i

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's g

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Ui i

e i

REGION CF i

i.

p p.............j... A C C EP T A B L E--+.

-i a8i j

OPERATION l

i j

4:

N i (350,3.5) -- ! --

z 1

o e

l r

L s 3:

i.

REGION OF i

z 8

'y.............>.............j............. $............. j. U N A C C E i

i i

OPERATION i

H2 o

i i

i' i

i i

I

'.............e.

(n p

y.............p............q.............<............

4.............t g?

?

l p.............p.............;..............t.............$.............t.............;

O' O

10 0 200 300 400 500 600 COLD LEG TEMPERATURE ('F)

FIGURE 3.1 - IA SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE 4

i pal.0 VERDE - UNIT 3 3/4 1-2a AMENDMENT NO. 2 i

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

When in MODE 1 or MODE 2 with k,ff greater than or equal to 1.0, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that CEA group withdrawal is within the Transient Insertion Limits of Specification 3.1.3.6.

When in MODE 2 with k,ff less than 1.0, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to c.

achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.

d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of e. below, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6.

I e.

When in MODE 3, 4, or 5, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of at least the following factors:

1.

Reactor Coolant System boron concentration, 2.

CEA position, 3.

Reactor Coolant System average temperature, 4.

Fuel burnup based onigross thermal energy generation, S.

Xenon concentration, and 6.

Samarium concentration.

4.1.1.2.2 When in MODE 3, 4, or 5, with any full-length CEA fully or partially withdrawn, and T less than or equal to 500*F, K shall be determined to cold N-1

. be less than 0.99 at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of at least the following factors:

1.

Reactor Coolant System boron concentration, 2.

CEA position, 3.

Reactor Coolant System average temperature, 4.

Fuel burnup based on gross tnermal energy generation, 5.

Xenon concentration,.snd 6.

Samarium concentration.

4.1.1.2.3 The overall core reactivity balance shall be compared to predicted volues to demonstrate agreement within i 1.0% delta k/k at least once per 31 Effective Full Power Days (EFPD).

This comparison shall consider at least those factors stated in Specification 4.1.1.2.1.e or 4.1.1.2.2.

The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each fuel' loading.

PALO VERDE - UNIT 3 3/4 1-3 AMENDMENT NO, 2

MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the area of A:ceptable Operation shown on Figure 3.1-1.

APPLICABILITY: MODES 1 and 2*#.

ACTION:

With the moderator temperature coefficient outside the area of Acceptable Operation skiwn on Figure 3.1-1, b2 in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements.

MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.

4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:

a.

Prior to initial operation above 5% of RATED THERMAL POWER, efter each fuel loading.

b.

At any THERMAL POWER, within 7 EFPD after reaching a core average exposure of 40 EFPD burnup into the current cycle.

c.

At any THERMAL POWER, within 7 EFPD after reaching a core avarage exposure equivalent to two-thirds of the expected current cycle end-of-cycle core average burnup.

With Keff greater than or equal to 1.0.

l

SecSpecialTest5xception3.10.2.

PALO VERDE - UNIT 3 3/4 1-4

l 3/4.1.2 BORATION SYSTEMS f

FLOW PATHS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE:

a.

If only the spent fuel pool in Specification 3.1.2.5a. is OPERABLE, a flow path from the spent fuel pool via a gravity feed connection and a charging pump to the Reactor Coolant System.

b.

If only the refueling water tank in Specification 3.1.2.5b. is OPERABLE, a flow path from the refueling water tank via either a charging pump, a high pressure safety injection pump, or a low pres-sure safety injection pump to the Reactor Coolant System.

APPLICABILITY:

MODES 5 and 6.

ACTION:

J With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEIL' LANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

I t

(

PALO VERDE - UNIT 3 3/4 1-7 4

i REACTIVITY CONTR3 SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION j

3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE:

i a.

A gravity feed flow path from either the refueling water tank or the spent fuel pool through CH-536 (RWT Gravity Feed Isolation Valve) and a charging pump to the Reactor Coolant System, b.

A gravity feed flow path from the refueling water tunk through CH-327 (RWT Gravity Feed / Safety Injection System Isciation Valve) and a charging pump to the Reactor Coolant System, c.

A flow path from either the refueling water tank or the spent fuel pool through CH-164 (Boric Acid Filter Bypass Valve), utilizing gravity feed and a charging pump to the Reactor Coolant System.

APPLICABILITY:

MODES 1, 2, 3, and,4.

ACTION:

With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant 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 at least two flow paths to OPERABLE l

status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.2.1 At least two of the above required flow paths shall be demonstrated OPERABLE:

a.

At least cnce per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

h.

At least once per 18 months when the Reactor Coolant System is at r.oreal operating pressure by verifying that the flow path required by Specificatior: 3.1.2.2 delivers at least 26 gpm for 1 charging.

pump and 68 gpm for two charging pumps to the Reactor Coolant System.

4.1.2.2.2 The provisions of h ecification 4.0.4 are not applicable for entry into Mode 3 or Mode 4 to perform the surveillance testing of Specificatien 4.1.2.2.1.b provided the testing is performed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving normal operating pressure in the reactor coolant system.

PALO VERDE - UNIT 3 3/4 1-8 AMENDMENT NO. 2

CHARGING PUMPS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one charging pump or one high pressure safety injection pump or one low pressure safety injection pump in the boron injection flow path required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY:

MODES 5 and 6.

ACTION:

With no charging pump or high pressure safety injection pump or low pressure safety injection pump OPERABLE or capable of being powered from an OPERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5.

4 e

PALO VERDE - UNIT 3 3/4 1-9 AMENDMENT NO. 2 I

i

+

4 CHARGING PUMPS - OPERATING l

LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps 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 at least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i SURVEILLANCE REQUIREMENTS 4.1.2.4 No additional Surveillance Requirements other than thoae required by Specification 4.0.5.

PALO VERDE - UNIT 3 3/4 1-10 AMENDMENT NO. 2

30 RATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 Each of the following borated water sources shall be OPERABLE:

a.

The spent fuel pool with:

1.

A minimum borated water volume as specified in Figure 3.1-2, and l

2.

A boron concentration of between 4000 ppm and 4400 ppm boron, and l

3.

A solution temperature between 60'F and 180'F.

b.

The refueling water tank with:

1.

A minimum contained borated water volume as specified in Figure 3.1-2, and 2.

A baron concentration of between 4000 and 4400 ppm of boron, and' l

3.

A solution temperature between 60*F and 120 F.

APPLICABILITY:

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

ACTION:

With the above required spent fuel pool inoperable, restore the pool a.

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 above required spent fuel pool l

to OPERABLE status within the next 7 days or be in COLD SHUT 00WN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the refueling wtter tank inoperable, restore the tank 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 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 4.1.2.6 Each of the above required borated water sources shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration in the water, and 2.

Verifying the contained borated water volume of the water source, b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the refueling water tank temperature when the outside air temperature is outside the 60'F to 120 F range.

c.

At least Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the spent fuel pool tempera-ture when irradiated fuel is present in the pool.

xSee Special Test Exception 3.10.7.

l PALO VERDE - UNIT 3 3/4 1-13 AMENDMENT NO. 2 l

BORON DILUTION ALARMS LIMITING CONDITION FOR OPERATION 3.1.2.7 Both startup channel high neutron flux alarms shall be OPERABLE.

APPLICABILITY: MODES 3*, 4, 5, and 6.

ACTION:

a.

With one startup channel high neutron flux alare inoperable:

f 1.

Determine the RCS boron concentration when entering MODE 3, 4, l

5. or 6 or at the time the alare is determined to be inoper-able.

From that time, the RCS boron concentration shall be j

determined at the applicable monitoring frequency in i

Tables 3.1-1 through 3.1-5 by either boronometer or RCS i

sampling.**

b.

With both startup channel high rieutron flux alares inoperable:

1.

Determine the RCS boron concentration by either boronneter and i

RCS sampiing** or by independent collection and analysis of two RCS samples when entering Mode 3, 4, or 5 or at the time both alarms are determined to be inoperable.

From that time, the RCS boron concentration shall be determined at the applicable monitoring frequency in Tables 3.1-1 through 3.1-5, as appli-j cable, by either boronneter and RCS sampling ** or by collection and analysis of two independent RCS samples.

If redundant determination of RCS boron concentration cannot be accomplished 3

immediately, suspend all operations involving CORE ALTERATIONS 4

l or positive reactivity changes until the method for determining and confirming RCS boron concentration is restored.

i!

2.

When in MODE 5 with the RCS level below the centerline of the j

hotleg or MODE 6, suspend all operations involving CORE 4

ALTERATIONS or positive reactivity changes until at least one startup channel high neutron flux alarm is restored to OPERABLE status.

{

c.

The provisions of Specification 3.0.3 are not applicable.

i SURVEILLANCE REQUIREMENTS 4.1.2.7 Each startup channel high neutron flux alarm shall be demonstrated OPERABLE by performance of:

i l

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the neutron flux is within the startup range following l

a reactor shutdown.

- With one or more reactor coolant pumps (RCP) operating the sample should be obtained from the hot leg. With no RCP operating, the sample should be g

obtained from the discharge line of the low pressure safety injection (LPSI) e pump operating in the shutdown cooling mode.

l l

PALO VERDE - UNIT 3 3/4 1-14 1

t SURVEILLANCE REQUIREMENTS (Continued) a.

A CHANNEL CHECK:

1.

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

2.

When initially setting setpoints at the following times:

a)

One hour after a reactor trip, b)

After a controlled reactor shutdown: Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after the neutron flux is within the startup range in MODE 3.

b.

A CHANNEL FUNCTIONAL TEST every 31 days of cumulative operation during shutdown.

i l

O l

1 f

I PALO VERDE - UNIT 3 3/4 1-15 m

v'

~,

-_-4-=

_,.,,,,.,.,m_

TABLE 3.1-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION A5 A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR K,ff > 0.98 OPERATIONAL Number of Operatina Charaina Pumps MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 hour ONA ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 hour ONA ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1 hour DNA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed i

]

1 PALO VERDE - UNIT 3 3/4 1-16 AMENDMENT NO. 2 1

4 1

1 TABLE 3.1-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMP 5 AND PLANT OPERATIONAL MODES FOR 0.98 > K,ff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 0

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months I hour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4

not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5

not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hout 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 & 5 on SCS 8 hcurs 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA t

dotes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed

}

i i

1 4

PALO VERDE - UNIT 3 3/4 1-17 AMENDMENT NO. 2 r

c y

r-m--

4 -

TABLE 3.1-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION A5 A FUNCTION OF OPERATING CHARGING PUMP 5 AND PLANT OPERATIONAL MODES FOR 0.97 > K,ff > 0.96 OPERATIONAL Number of Operatina Charaina Pumps MODE O

1 2

3

.3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 4

not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 5

not on SCS S hours 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months I hour 4&5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1 hour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed i

e PALO VERDE - UNIT 3 3/4 1-18 AMENDMENT NO. 2

TABLE 3.1-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION A5 A FUNCTION OF OPERATING CHARGING PUMPS 4

KND PLANT OPERATIONAL MODES FOR 0.96 > K,ff > 0.95 OPERATIONAL Number of Operating Charging Pumps MODE O

1 2

3 3

12 ilours 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours I hour 4

not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 5 hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour 5

not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 5 hours 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I hour 4&5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed-i i

I i

i a

i i

PALO VERDE - UNIT 3 3/4 1-19 AMENDMENT NO. 2

TABLE 3.1-5 REQUIRE 0 MONITORING FREQUENCIES FOR BACKUP BORON DILUTION OETECTION AS A FUNCTION OF OPERATING CHARGING PUMP 5 AND PLANT OPERATIONAL MODES FOR K,ff < 0.95 OPERATIONAL Number of Operating Charging Pumps MODE O

1 2

3 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 6 hours 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4

not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 6 hours 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5

not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 6 hours 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4&5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 6

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 8 hours 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 2 hours Note:

SCS = Shutdown Cooling System i

1 e

PALO VERDE - UNIT.1 3/4 1-20 AMENDMENT NO, 2

REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES CEA POSITION LIMITING CONDITION FOR OPERATION 3.1.3.1 All full-length (shutdown and regulating) CEAs, and all part-length CEAs which are inserted in the core, shall be OPERABLE with each CEA of a given group positioned within 6.6 inches (indicated position) of all other CEAs in its group.

In addition, the position of the part length CEAs Groups shall be limited to the insertion limits shown in Figure 3.1-2A.

APPLICABILITY:

MODES 1* and 2*.

2 l

l ACTION:

a.

With one or more full-length CEAs inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.2 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in l

at least HOT STANDBY with'in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With more than one full-length or part-length CEA inoperable or misaligned from any other CEA in its group by more than 19 inches (indicated position), be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one or more full-length or part-length CEAs misaligned from any c.

other CEAs in its group by more than 6.6 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with Figure 3.1-2B and that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned CEA(s) is either:

1.

Restored to OPERABLE status within its above specified alignment requirements, or 2.

Declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.2 is satisfied.

After declaring the CEA(s) l inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6 provided:

a)

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the remainder of the CEAs in the group with the inoperable CEA(s) shall be aligned to within 6.6 in,-

ches of the inoperable CEA(s) while maintaining the allow '

.able CEA sequence and insertion limits shown on Fig-ures 3.1-2A, 3.1.3, and 3.1-4; the THERMAL POWER le M shall be restricted pursuant to Specification 3.1,

dur-ing subsequent operation, "See Special Test Exceptions 3.10.2 and 3.10.4.

PALO VERDE - UNIT 3 3/4 1-21 AMENDMENT NO. 2

LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.2 l

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 i mperable 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.

f.

With part length CEAs inserted beyond insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1.

Restorethepartlen;,.hCEAstowithintheirlimits,or 2.

Reduce THERMAL POWER to less than or equal to tiat fraction of RATED THERMAL POWER which is allowed by part length CEA group position using Figure 3.1-2A.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each 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 movement of at least 5 inches in any one direction at least once per 31 days.

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

TABLE 3.3-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION TABLE NOTATIONS t

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

The provisions of Specification 3.0.4 are not applics.ble.

i (a) Trip may be manually bypassed above 10 4% of RATED THERMAL POWER; bypass shall be automstically removed when THERMAL POWER is less than or equal to 10 4% of RATED THERMAL POWER.

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

(c) Trip may be manually bypassed below 10 4% of RATED THERMAL POWER; bypass

(

shall be automatically removed when THERMAL POWER is greater than or equal to 10 4% of RATED THERMAL POWER.

l (d) Trip may be bypassed during te. sting pursuant to Special Test Exception 3.10.3.

(e) See Special Test Exception 3.10.2.

1 (f) There are four channels, each of which is comprised of one of the four reactor trip breakers, arranged in a selective two-out-of-four configuration (i.e., one-out-of-two taken twice).

ACTION STATEMENTS s

ACTION 1 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least i

HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and/or open the protective system trip breakers.

ACTION 2 With the number of channels OPERABLE one les'. than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

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

l I

t PALO VERDE - UNIT 3 3/4 3-5 AMENDMENT NO. 2

TABLE 3.3-1 (Continued)

REACTOR PROTECTIVE INSTRUMENTATION ACTION STATEMENTS i

With a channel process measurement circuit that, affects multiple functional units inoperable or in test, bypass or i

trip all associated functional units as listed below:

i Process Heasurement Circuit Functional Unit Bypassed / Tripped 1.

Linear Power Variable Overpower (RPS)

(Subchannel or Linear)

Local Power Density - High (RPS)

DNBR - Low (RPS) l 2.

Pressurizer Pressure - High Pressurizer Prest,ure - High (RPS)

(Narrow Range)

Local Power Density - High (RPS)

DNBR - Low (RPS) 3.

Steam Generator Pressure -

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

Steam Generator Level 2-Low (ESF) 4.

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

(Wide Range)

Steam Generator Level 1-Low (ESF) l Steam Generator Level 2-Low (ESF) 5.

Core Protection Calculator Local Power Density - High (RPS)

DNBR - Low (RPS)

{

ACTION 3 With the number of channels OPERABLE one less than the Minimum l

Channels OPERABLE requirement, STARTUP and/or POWER OPERATION may continue prov'.ded the following conditions are satisfied:

a.

Verify that one of the inoperable channels has been j

bypassed and place the other channel in the tripped condition within I hour, and b.

All tunctional units affected by the bypassed / tripped channel shall also be placed in the bypassed / tripped crndition as listed below:

Process Measurement Circuit Functional Unit Bypassed / Tripped 1.

Linear Power Variable Overpower (RPS)

(Subchannel or Linear)

Local Power Density - High (RPS)

DNBR - Low (RPS) 2.

Pressurizer Pressure -

Pressurizer Pressure - High (RPS)

High (Narrow Range)

Local Power Density - High (RPS)

DN8R - Low (RPS) k PALO VERDE - UNIT 3 3/4 3 6 l<

a 3/4.10 SPECIAL TEST EXCEPTIONS t

3/4.10.1 SHUTDOWN MARGIN AND K

- CEA WORTH TESTS l

N-1 LIMITING CONDITION FOR OPERATION I

3.10.1 The SHUT 00WN MARGIN and K requirements of Specification 3.1.1.2 may l

N-1 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 insertien from OPERABLE CEA(s), or the reactor is suberitical 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, 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 SHUTDOWN MARGIN and K -1 required by Specification 3.1.1.2 are restored, H

b.

With all full length CEAs fully inserted and the reactor suberitical 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 REQUIREMENTS i

4.10.1.1 The position of each full-length and part-lengtt, 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 leest the 50% 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 3.1.1.1.

4.10.1.3 When in MODE 3 or MODE 4, the reactor shall be determined to be suberitical 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 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.

)

l b.

CEA position, c.

Reactor Coolant System average temperature.

d.

Fuel burnDp based on gross thermal energy generation, I

)

e.

Xenon concentration, and f.

Samarium concentration, "Operation in MODE 3 and MODE 4 shall be limited to 6 consecutive hours, a

Limited to low power PHYSICS TESTING at the 320'F plateau.

i PALO VERDE - UNIT 3 3/4 10-1 AMENDMENT NO. 2

e 5

s' SPECIAL TEST EXCEPTIONS 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT. INSERTION, AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION J

I 3.10.2 The moderator temperature coefficient, group height, insertion, and power distribution limits of Specifications 3.1.3.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of I.C.1 (CEA Calculators) of Table 3.3-1 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWER is restricted to the, test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.

The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.

APPLICABILITY:

MODES 1 and 2.

ACTION:

With any of the limits of Specification 3.2.1 being exceeded while the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, and the Minimum Channels OPERABLE requirement of I.C.1 (CEA Calcu!ators) of Table 3.3-1 are suspended, either:

Reduce THERMAL POWER sufficiently to satisfy the requirements a.

1 of Specification 3.2.1, or b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during l

PHYSICS TESTS in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERABLE require-ment of I.C.1 (CEA Calculators) of Table l'.3-1 are suspended and shall be verified to be within the test power plateau.

4.10.i'.2 The linear heat rate shall be dettrained to be within the limits'of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.2 and 3.3.3.2 during PHYSICS TESTS above 20% of RATED THERMAL POWER in which the requirements of Specifications 3.1.1.3, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7, or the Minimum Channels OPERA 8LE requirement of I.C.1 (CEA Calculators) of Table 3.3-1 are suspended.

PALO VERDE - UNIT 3 3/4 10-2

SPECIAL TEST EXCEPTIONS 3/4.10.9 SHUT 00WN MARGIN AND K

- CEDMS TESTING N-1 LIMITING CONDITION FOR OPERATION 3.10.9 The SHUTD0WN MARGIN requirement of Specification 3.1.1.1 and the SHUTDOWN MARGIN and K requirements of Specification 3.1.1.2 may be sus-N-1 pended for pre-startup testy to demonstrate the OPERABILITY of the control l

element drive mechanism system provided:

a.

No more than one CEA is withdrawn at any time.

b.

No CEA is withdrawn more than 7 inches.

c.

The K requirement of Specification 3.1.1.2 is met prior to the N-1 start of testing.

d.

All other operations involving positive reactivity changes are suspended during the testing, i

APPLICABILITY:

MODES 4 and 5.

r ACTION: With any of the above requirements not met, suspend testing and comply with the requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, t

SURVEILLANCE REQUIREMENTS 4

t 4.10.9 Surveillance Requirements 4.1.1.2.1.e and 4.1.1.2.2 shall be conducted within one hour prior to the start of testing, and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during testing, h

1 i

1 a

i PALO VERDE - UNIT 3 3/4 10-9 AMENDMENT NO. 2

3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN AND KH-1 The function of SHUTDOWN MARGIN is to ensure that the reactor remains suberitical following a design basis accident or anticipated operational occur-The function of K -1 is to maintain sufficient suberiticality to pre-rence.

N clude inadvertent criticality following ejection of a single control element assembly (CEA).

During operation in MODES 1 and 2, with k,ff greater than or l

equal to 1.0, the transient insertion limits of Specification 3.1.3.6 ensure that sufficient SHUTDOWN MARGIN is available.

SHUTDOWh MARGIN is the amount by which the core is suberitical, or would be subcritical immediately following a reactor trip, considering a single malfunction resulting in the highest worth CEA failing to insert.

K is a N-1 measure of the core's reactivity, considering a single malfunction resulting in the highest worth inserted CEA being ejected.

SHUTDOWN MARGIN requirements v,ary throughout the core life as a function of fuel depletion and reactor coolant system (RCS) cold leg temperature (Teold)*

The most restrictive condition occurs at EOL, with T at no-load operating cold temperature, and is associated with a postulated steam line break accident and the resulting uncontrolled RCS cooldown.

In the analysis of this accident, the specified SHUTDOWN MARGIN is required to control the reactivity transient and ensure that the fuel performance and offsite dose criteria are satisfied.

As (initial) T dereases, the potential RCS cooldown and the resulting cold i

reactivity transient are less severe and, therefore, the required SHUTDOWN 4

MARGIN also decreases.

Below T of about 210*F, the inadvertent deboration eold event becomes limiting with respect to the SHUTDOWN MARGIN requirements.

Below 210'F, the specified SHUTDOWN MARGIN ensures that sufficient time for operator 4

actions exists between the initial indication of the deboration and the total loss of shutdown margin.

Accordingly, with at least one CEA partially or fully withdrawn, the SHUTDOWN MARGIN requirements are based upon these limiting conditions.

Additional events considered in establishing requirements on SHUTDOWN MARGIN that are not limiting with respect to the Specification limits are single CEA withdrawal and startup of an inactive reactor coolant pump.

K requirements vary with the amount of positive reactivity timt would N-1 be introduced assuming the CEA with the highest inserted worth ejects from the In the analy'is of the CEA ejection event, the K,y requireme1t ensures core.

s g

that the radially averaged enthalpy acceptance criterion is satisfied, consider-ing power redistribution effects.

Above T of 500*F, Doppler reactivity eold l

feedback is sufficient to preclude the need for a specific K -1 muhnL N

l With all CEAs fully inserted, K,y aad SHUTDOWN MARGIN requirements are equiva-y lent in terms of minimum acceptable core boron concentration.

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

1 REACTIVITY CONTROL SYSTEMS i

BASES SHUTDCWN MARGIN AND KN-1 (continued)

Other technical specifications that reference the Specifications on SHUT-DOWN MARGIN or K are:

3/4.1.2, B0 RATION SYSTEMS, 3/4.1.3, MOVABLE CONTROL i

N-1 ASSEMBLIES, 3/4.9.1, REFUELING OPERATIONS-BORON CONCENTRATION, 3/4.10.1, SHUT-DOWN MARGIN AND K

- CEA WORTH TESTS, and 3/4.10.9, SHUT 00WN MARGIN AND N-1 K

- CEDMS TESTING.

N-1 3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC)

{

The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle.

The surveillance requirements for measurement of the MTC during each fuel c9cle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

The confirmation that the measured MTC value is within its limit provides assurances that the coeffi-cient will be maintained within acceptable values throughout each fuel cycle.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant Sys. tem cold leg temperature less than 552*F.

This limita-tion is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, and (3) consistency with the FSAR safety analysis.

.j PALO VERDE - UNIT 3 B 3/4 1-la AMENDMENT NO. 2

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 B0 RATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation.

The components required to perform this function include (1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) an emergency power supply from OPERABLE diesel generators, and (5) the volume control tank (VCT) outlet valve CH-UV-501, capable of isolating the VCT from the charging pump suctlon line.

The nominal capacity of each charging pump is 44 gpm at its discharge.

Up to 16 gpm of this may be diverted to the volume control tank via the RCP control bleedoff.

Instrument inaccuracies and pump performance uncertainties are limited to 2 gpm yielding the 26 gpm value.

With the RCS temperature above 210 F, a minimum of two separate and redundant boron injection systems are pro'vided to ensure single functional capability in the event an assumed failure renders one of the systems inoper-able.

Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.

Each system is capable of providing boration equivalent to a SHUTDOWN MARGIN of 4% delta k/k after xenon decay and cooldown to 210 F.

Therefore, the boration capacity of either system is more than sufficient to satisfy the SHUT-DOWN MARGIN and/or K requirements of the specifications.

The maximum ex-N-1 pected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 23,800 gallons of 4000 ppm borated water from either the refueling water tank or the spent fuel pool.

With the RCS temperature below 210 F one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single injection system becomes inoperable.

The restrictions of one and only one operable charging pump whenever reactor coolant level is below the bottom of the pressur-izer is based on the assumptions used in the analysis of the boron dilution event.

Each system is capable of providing boration equivalent to a SHUTDOWN MARGIN of 4% delta k/k.

Therefore, the boration capacity of the system re-quired below 210 F is more than sufficient to satisfy the SHUTDOWN MARGIN and/or K

requirements of the specifications.

This condition requires 9,700 gal.lons N-1 of 4000 ppm borated, water from either the refueling water tank or the spent fuel pool.

PALO VERDE - UNIT 3 B 3/4 1-2 AMENOMENT N0. 2

3/4.10 SPECIAL TEST EXCEPTIONS i-BASES 3/4.10.1 SHUT 00WN 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 TEM)ERATURE COEFFICIENT, GROUP HEIGHT, INSERTION, AND POWER OISTRIBUTION 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.

O 3/4 10.3 REACTOR COOLANT LOOPS Q

rnis 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 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 AND PRESSURE FOR CRITICALITY This special test exception permits reactor criticality at low THERMAL POWER levels with T below the minimum critical temperature and pressure during PHYSICS TESTS,Mich are required to verify the low temperature physics predictions and'to ensure the adequacy of design codes for reduced temperature conditions.

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

1.

Biological shielding survey test 2.

Isothermal temperature coefficient tests 3.

CEA group tests

(

4.

Boron worth tests 5.

Critical configuration boron concentration PALO VERDE - UNIT 3 8 3/4 10-1

SPECIAL TEST EXCEPTIONS l

BASES 3/4.10.6 SAFETY INJECTION TANKS This special test exception permits testing the low pressure safety injection system check valves.

The pressure in the injection header must be reduced below the head of the low pressure injection pump in order to get flow through the check valves.

The safety injection tank (SIT) isolation valve must be closed in order to accomplish this.

The SIT isolation valve is still capable of automatic operation in the event of an SIAS; therefore, system capability should not be affected.

3/4.10.7 SPENT FUEL POOL LEVEL This special test exception permits loading of the initial core with the spent fuel pool dry.

3/4.10.8 SAFETY INJECTION TANK PRESSURE This special test exception allows the performance of PHYSICS TESTS at low pressure / low temperature (600 psig, 320 F) conditions which are required to verify the low temperature physics predictions and to ensure the adequacy of design codes for reduced temperature conditions.

3/4.10.9 SHUTDOWN MARGIN AND K

- CEDMS TESTING N-1 This special test exception allows the performance of control element drive mechanism tests prior to startup, without the operator having to be concerned as to whether Specification 3.1.1.1 or 3.1.1.2 is applicable as CEAs are moved.

The logarithmic power level-high trip provides additional protec-tion against inadvertent criticality during this test.

1 PALO VERDE - UNIT 3 B 3/4 10-2 AMENDMENT NO. 2 7

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ML20149D081

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