ML17311A322

Amends 82,69 & 54 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Allowing Credit to Be Taken for Burnup of Spent Assemblies in Establishing Storage Locations within Spent Fuel Storage Pool

ML17311A322
Person / Time
Site:	Palo Verde
Issue date:	09/30/1994
From:	Quay T Office of Nuclear Reactor Regulation
To:
Shared Package
ML17311A323	List: ML17311A322 ML17311A325
References
NUDOCS 9410120295
Download: ML17311A322 (60)

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UNITED STATES NUCLEAR REGULATORY COMMlSSION WASHINGTON, D.C. 20555-0001 94ioi20295.05000528 pgR ADOCK pDR

'p RIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO; STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE 2.

Amendment No.

82 License No. NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El'aso Electric

Company, Southern California Edison

Company, Publ.ic Service Company of New Mexico, Los Angeles Department of Water and

Power, and Southern California Public Power Authority dated February 18,

1994, as supplemented by letter dated June 20,

1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

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

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

The issuance of this amendment is in accordance

.with 10 CFR Part 51 of the Commission's regulations and all applicable "requirements have been satisfied.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

NPF-41 is hereby amended to read as follows:

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3.

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

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

APS shall operate the facility in accordance wi'th the Technical Specifications and the Environmental Protection Plan,, except where otherwise stated in specific license conditions.

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

FOR THE NUCLEAR REGULATORY 'COMMISSION

Attachment:

Changes to the Technical Specifications Theodore R. quay, Director.

Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of Issuance:

September 30, 1994

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

82 TO FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical l.ines indicating the areas of change.

Remove IX XIV XIX B 3/4 9-3 5-5 5-6 Insert IX'IV XIX 3/4 9-17 B 3/4 9-3 5-5 5-6 5-6a

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li I I INDEX I~,4 41 LIMITING CONDITIONS F PERATION AND SURVEILLANCE RE MENTS SECTION ELECTRICAL POWER SYSTEMS (Continued) 3/4.8.2 D.C.

SOURCES PERATING............................................

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PAGE 3/4 8-9 3/4 8-13 3/4 8-14 3/4 8-16 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES.............................-...

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES.................................

3/4 8-17 3/4 8-40 3 4.9 REFUELING OPERATIONS 3/4.9. 1 BORON CONCENTRATION.....................................

3/4.9.2 INSTRUMENTATION.........................................

3/4.9.3 DECAY TIME.......

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

3/4.9. 5 COMMUNICATIONS.................................-.........

3/4.9.6 REFUELING MACHINE.......................................

3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE POOL BUILDING.........

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL....

LOW WATER LEVEL.........

3/4 9-1 3/4 9-2 3/4 9-3 3/4 9-4 3/4 9-5 3/4 9-6 3/4 9-7 3/4 9-8 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......................................

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C 3/4.9. 11 WATER LEVEL STORAGE POOL......................

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

3/4.9.13 BORON CONCENTRATION SPENT FUEL STORAGE POOL...

3 4.10 SPECIA TEST EXCEPTIONS 3/4 10 1

SHUTDOWN MARGIN AND K~ )

CEA WORTH TESTS ~ ~

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

3/4. 10.3 REACTOR COOLANT LOOPS...................................

3/4 9-11 3/4 9-12 3/4 9-13 3/4 9-14 3/4 9-17

.3/4 10-1 3/4 10-2 3/4 10-3 PALO VERDE UNIT 1

IX AMENDMENT NO. 28,. 82

II'tDEX LIMITING CONDITIONS I=OR OPERATION ANID SURVEILLAN E E UIREHENTS SECTION 3/4.10'.4 CEA POSITION, REGUL'ATING CEA iNSERTION LIMITS

'ND REACTOR COOLANT COLD LEG TEMPERATURE......,.....

3/4.10.5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITIICALITY.'..

3/4.10.6 SAFETY INJECTIOhl TANKS........,.....'..'...'..'.'...'...'..

3/4. 10.7 SPENT FUEL POOL LEVEL.......-...............l..'.......

3/4. 10.8 SAFETY INJECTIOhl TANK', PRESSURE.....................

10 9

SHUTDOWN MARGIN AND K'N-l.

C DMS TEST hlG 3/4.10.10 NATURAL CIRCULATION TESl'ING PROGRAM...........,.....

3/4. 11 RADIOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID HOLDUP TANKS.....,................................

3/4. 11. 2 EXPLOSIVE GAS MIXTURE...,.................,......

3/4. 11. 3 GAS STORAGE TANK'.5........,..;..............,..............

PAGE 3/4 10-4 3/4 10-5 3/4 1~0-6 3/4 li0-7 3/4 10-8 3/4 10-9 3/4 l(0-10 3/4 11-1 3/4 11-2 3/4 11-3 PALO VERDE - UNIT 1 X

AMENDMENT NO.

Sg 62

BASES INDEX SECTION 3 4.7 LANT SYSTEMS 3/4.7.1 TURBINE CYCLE...........................................

AGE 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.............................

3/4.7.5 ULTIMATE HEAT SINK......................................

B 3/4 7-4 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 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..................................

3/4.7.12 CONTROL ROOM AIR TEMPERATURE............................

3 4.8 ELECTRICAL POWER SYSTEMS B 3/4 7-7 B 3/4 7-7 3/4.8. 1, 3/4.8.2, and 3/4.8.3 A.C.

SOURCES, D.C.

SOURCES ONSITE POWER DISTRIBUTION SYSTEMS........

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

B 3/4 8-3 3 4.9 REFUELING OPERATIONS 3/4.9.2 3/4.9.3 INSTRUMENTATION.........................................

ECAY TIHE....................................-

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D 3/4.9. 1 BORON CONCENTRATION.....................................

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

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

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3/4.9.6 REFUELING MACHINE.......................................

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

23

BASES 0

INDEX SECTION 3/4 9 7 CRANE TRAVEL SPENT FlJEL S10RAGE POOL BlJILDING 3/4.9o8 SHUTDOWN COOLINiG AND COOLANT CIRCULATION>>,............ o..

3/4.9.9 CONTAINMENT PURGE VALVE I'SOLATION SYSTEMS.....'..'...'....

3/4.9.10 and, 3/4.9. 11 WATER LEVEL REACTOR VESSEL and STORAGE POOL o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~

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PAGF 8 3/4 9-2 8 3/4 9-2 8 3/4 9-3 8 3/4 9-3 3/4.9.12 FUEL BUILDING ESSENTIAL VIENTILATIONSYSTEM...... >>....

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8 3/4 '9-3 3/4.9.13 BORON CONCENTRATION - SPEI'IT FUEL STORAGE POOL.........,..

8 3/4 '9-3 3 4.10 SPECIAL TEST EXCEPTIONS 3/4 10 1

SHUTDOWN MARGIN"AND I(g

)r CEA WORTH TESTS 3/4.10.2 MODERATOR TEHPERATURIE COEI=FICIENT, GROUP HE][GHT, INSERTION, AND POWER DISTRIBUT10N LIMII'... o.... o.......

3/4. 10.3 REACTOR COOLANT LOOPS....o..,.........,....,;..'...',......

3/4.10.4 CEA POSITION, REGULAIING CEA INSERTION'Ll'HITS AND REACTOR C00'LANT COLD LEG TEMPERATURE...>>............

8 3/4 10-1 8 3/4 10-1 8 3/4 10-1 8 3/4 10-1 3/4.10o5 MINIMUM TEMPERATURE AND PRESSURE FOR CRITICALITY........

8 3/4 10-1 3/4.10o6 SAFETY INJECTION TANKS....,..;..........................

8 3/4 10-2 3/4. 10.7 SPENT FUEL POOL LEVEI............

3/4.10.8 SAFETY. INJECTIOI'J TANK PRESSURE..

3/4.10.9 SHUTDOWN HARGIN AND Ku.c - CEDHS 3 4.11 RADIOACTIVE iEFFLUI=NTS

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TESTING....o............

8 3/4'0-2 8 3/4 10-2 8 3/4 10-2 3/4.11.1 LIQUID HOLDUP TANKS............

3/4. 11. 2 EXPLOSIVE GAS Mi[XTURE................. ~.....;..........

3/4.11.3 GAS STORAGIE TANKS...........,..................,..........

8 3/4 11<<1 8 3/4 ll-l 8 3/4 ll-l PALO VERDE UNIT 1 XIV AMENDMENT NO. KM68, 82

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LIST OF FIGURES INDEX PAGE 3.1-1 3.2-1 3.4-1 3.4-2a 3.4-2b 3.4-2c 3.4-2d HINIMUH BORATED WATER VOLUMES.......................,...

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

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

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

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

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

REACTOR COOLANT SYSTEM MAXIMUM ALLOWABLE HEATUP AND COOLDOWN RATES FOR LESS THAN 8 EFPY OF 0 PERATION........................,..........................

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

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

LOW POPULATION ZONE o

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

ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT..............

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

3/4 7-26 PALO VERDE UNIT 1

XIX AMENDMENT NO. SS,,

82

o LIST OF TABI.ES ItfDEX PAGE 1.2 2.2 1

3. 3-1

3. 3-2

4. 3-1 3 ~ 3 3

3. 3-4

3. 3-5 4.3-2 3.3-6 4.3-3 3.3-7 4.3-4

3. 3-8

4. 3-5

3. 3"9A

3. 3-9B FREQUENCY hlOTATIONo............ o......... ~....... ~....

o.

OPERATIONAL MODES.o............o....o............o....o.

REACTOR PROTECTIVE INSTRUMENTATION TfIlIP SLtTPUIhtT LIHITSo ~ ~ ~ ~

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REACTOR PROTECTIVE INSTRUMIENTATION..........o.... o....

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REACTOR PROTECTIVE INSTRUMENTATION RCSPON.iE 't'IHESo.....

REACTOR PROTECTIVE INSTRUMENT'ATION SlIRVEILLAINCE R EQUIREMENTSo ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~

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ENGINEERED SAFETY FEATURES ACTUATION SY'ST)H INSTRUMENTATION...........,......,.................,....

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ENGINEERED SAFETY FEATURES ACTUATION'SYSTE'M INSTRUMENTATION 'TRIP VALUES....<<............o....o......

ENGINEERED SAFETY FEATURES RESPONSE 'fIHIES.'...',....o......

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREh'IENTS...o...........

RADIATION MONITORIhlG INSTRUMENTATION.'...'...'...'...'...'......

RADIATION MONITOIRING INSTRUMENTATION SURVEI LICENCE REQUIREMENTS SEISMIC MONITORING INSTRUMENTATION..........,...........

SEISMIC HONITORING INSTRUMENTATION SUiRVEILLANCE REQUIREMENTS'

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METEOROLOGIiCAL MONITORING INSTRUMENTATION...............

METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQIJIREMENTS.............. o............ o...

REMOTE SHUTDOhlN INSTRUMENTATION......................

REMOTE SHUTDOWN l)ISCONNECT SWITCHES................,....

1-9 2-3 3/4 3-3 3/4 3-13.

3/4 3-14 3/4 3-18 3/4 3-25 3/4 3-25 3/4 3-3:L 3/4 3-38 3/4 3-40 3/4 3-43 3/4 3~44 3/4 3-4(i 3/4 3~47 3/4 3~49 3/4 3~50 PALO VERDE - UNIT 1 XX AMENDMENT NO.

27, 69

E UELING OPERATIONS 3 4.9. 13 BORON CONCENTRATION SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9. 13 The boron concentration in the spent fuel storage pool shall be maintained greater than or equal to 2150 ppm.

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With the requirements of this specification not satisfied, suspend all movement of fuel assemblies in the spent fuel storage pool and restore the boron concentration to 2150 ppm or greater.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9. 13 The boron concentration of the spent fuel storage pool shall be determined by chemical analysis at least once per 7 days when fuel assemblies are in the spent fuel storage pool.

PALO VERDE UNIT 1 3/4 9-17 AMENDMENT NO.

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REFUELING OPERATIONS BASES A shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8-hour period during surveillance testing of ECCS pumps.

This is necessary to meet Surveillance 4.5.2, flow testing of the HPSI pumps without other pumps

running, and 4.3.3.5,,testing of the containment spray pumps and LPSI pumps during surveillance of the remote shutdown system.

3 4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.

The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3 4.9. 10 and 3 4'.9. 11 WATER LEVEL REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth (at least 23 feet above the top of the spent fuel) is available to remove a

nominal 99X of the assumed IOX iodine gap activity released from the rupture of an irradiated fuel assembly for a maximum fuel rod pressurization of 1200 psig.

The minimum water depth is consistent with the assumptions of the safety analysis.

3 4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM The limitations on the fuel building essential ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.

The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) to meet the guidance of Regulatory Guide 1.52, Revision 2, Positions C.6.a and C.6.b, has been found acceptable as documented in Revision 2 to Section 6.5. 1 of-the Standard Review Plan (NUREG-0800).

3 4.9. 13 BORON CONCENTRATION SPENT FUEL STORAGE POOL The restriction on the boron concentration of the spent fuel storage.pool ensures that k,<< is maintained less than or equal to 0.95 in the event that either a new or spent fuel assembly is either improperly loaded into any available storage location in the spent fuel storage pool, or is dropped in the gap between the pool wall and a Region 3 storage rack.

This boron concentration is more than adequate to ensure that the k << limit of 0.95, delineated in Specification 5.6. l.l.a, will not be vi'olated.

PALO VERDE UNIT 1 B 3/4 9-3 AMENDMENT NO-43-,

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DESIGN FEATURES 5.3 REACTOR CORE UEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel may be made if justified by a cycle specific reload analysis.

Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approximately 1950 grams uranium.

Each burnable poison rod shall have a nominal active poison length of 136 inches.

The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum radially aver aged enrichment of 4.30 weight percent U-235 at any axial location.

CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4. 1 The Reactor Coolant System is designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable surveillance requirements, b.

For a pressure of 2500 psi a, and c.

For a temperature of 650'F, except for the pressurizer which is 700'F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900

+ 300/-0 cubic feet at a nominal T,, of 593 F.

PALO VERDE UNIT I 5-5 AMENDMENT NO. 84 ~,

82

DESIGN FEATURES

5. 5 METEOROLOG ICAL~OWEf< LOCATION 5.5. 1 The meteorological tower shall be located a0 shown on Figure 5.1-1.

5.6 FUEL STORAGE 5.6.1 CRITICALITY 5.6. 1. 1

.The spent fuel storage racks are designed and shall be maintained with:

a.

The maximum calcu'lated k<< value, ih'eluding margin 'for uncertainty in calculational ihethod and mechanikal tllerances, less than or equal to 0.95 with a 95X probability at a~95k konficlence level when fllooded with unborated water.

b.

A nominal 9.!5 inches center-to-center distance between adjacent storage cell locations.,

5.6. 1.2 The k,<< for new fuel for the first, core loading stored dry in the spent fuel storage racks shall not exceed 0.98 wheti aqueous foam moderation is assumed.

5.6. 1.3 The spent fuel storage pool is organized into three regions for spent fuel storage.

Fuel shall be placed in the appropriate region based on apProj-priate initial enrichment and existing burnup as deisignated in Figure 5.6-1:

a.

Region I: Fuel shall be stored in a checkerboard (two-out-af-four) storage pattern.

Fuel that qualifies to be stored in Regions 1, 2, or 3, in accordarlcei with'igure 5.6-1, may be stored in Region 1.

b.

Region 2: Fuel shall be stored in a three-out-of-four storage pattern.,

Fuel that quali.fies to be 'st6red in Regions 2 or

'3,'n accordance with Figure 5.6-1, may be stored in Region 2.

c.

Region 3: Fuel shall be stored in a four-out-of-four storage pattern.

Only fuel that qualifies to be stored in Region 3, in accordance with Figure 5.6-1, sha'Ill be stored in Region 3.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be mainta.ined to prevent inadvertent draiining. of the pool below e1levation 137 feet 6 inch4sJ CAPACITY 5.6.3 The spent fue'I storage pool.is designed and,shall be maintained with a storage capacity limited to no more than 1329 fuel assemblies,.

5 7 COMPONENT CYCLIC OR IRANS];ENT LIMITS 5.7. 1 The components identified in Table 5.7-1 aire designed and shall be maintained within the cyclic or transient limits of Tables 5.7-1 and 5.7-2.

PALO VERDE UNIT 1 5-6

,AMENDMENT NO. 82

FIGURE 5. 6-1 ASSEMBLY BURNUP YERSUS INITIAL ENRICHMENT 50000 4.30

~ 45000

>40000 W 35OOO 0\\

D 30000 C

~ 25000 CQ

~20000 E 15000

~~ 10000 REGION 3 REGION 2 REGION 1 5000 0

2.00 2.50 3.00 3.50 4.00 Initial Enrichment, wt 4.50 5.00 QQQQO 4/4

~sass g/g PALO VERDE UNIT I 5-6a AMENDMENT NO. 82

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No.

NPF-51 The Nuclear 'Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison

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

Power, and Southern California Public Power Authority dated February 18,

1994, as supplemented by letter dated June 20,

1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Part I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

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

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:

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3.

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 69, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

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

Plan, except where otherwise stated in specific license conditions.

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

FOR THE NUCLEAR REGULATORY COMMISSION A-~- 4 ~r 'y Theodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 30, 1994

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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

69 TO FACILITY OPERATING LICENSE NO.

NPF-51 DOCKET NO.

STN 50-529 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

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

Remove IX XIV XIX B 3/4 9-3 5-5 5-6 Insert IX XIV XIX 3/4 9-17 B 3/4 9-3 5-5 5-6 5-6a

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LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS S

CTION L CTR CA P

W R

SYS MS (Continued) 3/4.8.2 D.C.

SOURCES P E RATING ~

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3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS PERATING............................................

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3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES..................................

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES.................................

3 4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION......................................

3/4.9.2 INSTRUMENTATION.........................................

3/4.9.3 DECAY TIME...............................................

3/4.9. 4 CONTAINMENT BUILDING PENETRATIONS.......................

3/4o9o5 COMMUNICATIONSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~

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3/4.9.6 REFUELING MACHINE.......................................

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING.........

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION HIGH WATER LEVEL............................

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LOW WATER LEVEL 3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................

3/4.9,10 WATER LEVEL - REACTOR VESSEL FUEL ASSEMBLIES...................................,,.

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3/4.9. 11 WATER LEVEL - STORAGE POOL..............................

3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATIONSYSTEM..............

3/4.9.13 BORON CONCENTRATION SPENT FUEL STORAGE POOL...........

3 4.

0 SP CIA T ST XCEPTIONS 3/4.10.

1 SHUTDOWN MARGIN AND K q CEA WORTH TESTS..............

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

AGE 3/4 8-9 3/4 8-13 3/4 8-14 3/4 8-16 3/4 8-17 3/4 8-40 3/4 9-1 3/4 9-2 3/4 9-3 3/4 9-4 3/4 9-5 3/4 9-6 3/4 9-7 3/4 9-8 3/4 9-9 3/4 9-10 3/4 9-11 3/4 9-12 3/4 9-13 3/4 9-14 3/4 9-17 3/4 10-1 3/4 10-2 3/4.10.3 REACTOR COOLANT LOOPS PALO VERDE - UNIT 2 3/4 10-3 AMENDMENT NO. 43-,

69

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE, REtLUIREMENTS SECTION 3/4.10.4 CEA POSITION, REGULATING.CEA INSERTION LIMITS'ND REACTOR COOLANT COLO LEG TEMPERATURE.......-. ""."

3/4.10. 5 MINIMUM TEMPERATURE AHD IPRESSURE -FOR C',RI'fICAL1TY,.

3/4.10. 6 SAFETY INJECTION TANK'......................

3/4.10.7 SPENT FUEL POOL LEVEL..............'..-.- ".

PAGE 3/4 10-4 3/4 10-6 3/4 Xe-7 3/4. 10. 8 SAFETY INJECTION TANK PRESSURE.....;...........,.......

3/4 10-8

-3/4. 10.9 SHUTDOWN MARGIN AND KN 1 -

CEDMS TESTING................

3/4. 11 RADIOACTIVE EFFLUENTS 3/4. 11. 1 LIQUID HOLDUP TANKS..............................,.......

3/4 10-9 3/4 11-1 3/4. 11. 2 EXPLOSIVE GAS MIXTURE......................

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3/4 11-2 3/4, 11.3 GAS STORAGE TANK I......,,..;...,,

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3/4 11-3 PALO VERDE - UNIT 2 AMENDMENT NO.

1.'8, 48

BASES INDEX SECTION 3 4.7 PLANT SYSTEMS 3/4.7. 1 TURBINE CYCLE...........................................

PAGE 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.............................

3/4.7.5 ULTIMATE HEAT SINK..

B 3/4 7-4 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 3/4.7.9 SNUBBERS................................................

3/4.7.10 SEALED SOURCE CONTAMINATION.............................

B 3/4 7-5 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 3 4.9 REFUELING OPERATIONS 3/4.9.2 3/4.9.3 INSTRUMENTATION.........................................

ECAY TIME

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D 3/4.9. 1 BORON CONCENTRATION.....................................

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

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

3/4.9.6 REFUELING MACHINE.......................................

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

13

BASES SECTION PAGE 3/4 9 7 CRANE TRAVEL SPENl FUEL STORAGE POOL BlJILDING 8 3/4 9

2 3/4.9.8 SHUTDOWN COOLING,AND COOLANT CIRCULATION'..'...'..'........

8 3/4 9-2 3/4.9.9 CONTAINMEI'tT PURGE VALVE ISOLATIOht SYSTEM...............

8 3/4 9-3 3/4.9. 10 and 3/4.9. 11 WATER LEVEL REACTOR VESSEL and STORAGE POOL............

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

8 3/4 9-3 8 3/4'9-'3 3/4.9.13 BORON CONCENTRATION SPENT FUEL STORAGE POOL,..........

8 3/4i9-i3 3 4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIhl AND KN-1 CEA WORTH TESTS.'...,..........

8 3/4 10-1 3/4.10.2 MODERATOR TEMPERATURE COEFFICIENT, GROUP HEIGHT, INSERTION,,

AND POWER DISTRIBUTION LIMITS.....,..........

3/4. 10.3 REACTOR COOLANT LOOPS..

3/4.10.4 CEA POSITION, REGULATING CEA INSERTION LlhtITS AND REACTOR COOLANT COLD LEG TEMPERATURES...............

8 3/4 10-1 8 3/4 10-1 8 3/4 10il 3/4.10.5 htINIMUM TEMPERATURE AND PRESSURE FOR CRITIC'ALITY.........

8 3/4 10-1 3/4.10.6 SAFETY INJECTION TANKS............. L.... 3...............

3/4. 10.7 SPENT FUEL POOL LEVEL.............,.....,...............

,8 3/4 10-2 8 3/4 10-2 3/4.10.8 SAFETY IN'JEC'TION TANK PRESSURE.....

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8 3/4 10-2 3'/4;10.9 SHUTDOWN t1ARGIN AND KN CEDMS TESTI'NG 3 4.11 RADIOACTIVE EFFLUENTS II ~

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3/4.11.2 EXPLOSIVE GAS MIXTURE................,..................

3/4. 11.3 GAS STORAGE TANKS......,..............................,..

8 3/4 ll-l 8 3/4 ll-l 8 3/4 ll-l PALO VERDE UNIT 2 XIV AMENDMENT NO. 03-,-48, 69

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

REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POWER EV EL ~

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

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

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

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

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

0 REACTOR COOLANT SYSTEM MAXIMUM ALLOWABLE HEATUP AND COOLDOWN RATES FOR 8 TO 32 EFPY OF 0PERATION..............................................

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

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

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

ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT..............

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

3/4 7-26 PALO VERDE UNIT 2 XIX AMENDMENT NO. 48, ~

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2. 2-1 FREQUENCY NOTATION..................

OPERATIONAL MODES............ o.........

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REACTOR PRO I ECTIVE INSTRiUMENTATION TRIP SETPOINT o ~

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3. 3-1

3. 3-2 4.3-1 3.3 3

REACTOR PROTECTIVE INSTRlUMENTATION.....3.. 3.....'.

REACTOR PROTECTIVE INSTRlUMENTATION REISPONSE 'fIMES.'.. o ~ ~ ~

REACTOR PRO I ECTIVE INSTRIUMENTATION SURVEILULNICE'EQUI REMENTS ~

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ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION.........o....o.--...........-.-*...-.

IMITS~

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L 2.3 3/4 3-3 3/4 3 11.

3/4 3-14 3/4 3-18

3. 3-4

3. 3-5

4. 3-2

3. 3-6

4. 3-3

3. 3-7

4. 3"4

3. 3-8

4. 3-5

3. 3-9A 3.3-9B ENGINEERED SAFETY FEATURI.:S ACTUATION SYSTEM INSTRUMENTAIION TRIP VALUES..o.......,..................

ENGINEERED SAFETY FiEATURI.:S RESPONSE TIMES...'...,....

ENGINEERED SAFETY FiEATURI=S ACTUATION SYSTEM INSTRUMENTA'll'ION SUR'VEILLANCE REQUIREHIEN1"S. -.....,....

RADIATION MONITORING INSTRUMENTATION.'...'...'...'.. o....

RADIATION N)NITORING INSTRUHENTA'TION SURVEILLANCE REQUIREMENTS.........

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SEISMIC MONITORIhlG INSTRUMENTATION...,i..i.. s.........

SEISMIC HONITORIhlG INSTRUMENTATION SUAVE.ILI~CE'EQUIREMENTS.

METEOROLOGICAL MONITORING INSTRUMEhlTATION..'... '.......

METEOROLOGICAL MONITORING INSTRUHENTA7ION SURVEILLANCE REQUIREMENTS............ o.....o.........

REMOTE SHUTDOWN INSTRUMENTATION...........

3/4 3-25 3/4 3 28 3/4 3-31 3/4 3-38 3/4 3-40 3/4 3-43 3/4 3-44 3/4 3*46'/4 3-47 3/4 3-49 REHOTE SHUTDOWN DISCONNECT SWITCHES.....................

3/4 3"50 PALO VERDE " UNIT 2 XX AMENDMENT NO.

XS

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3 4.9 REFUELING OPERATIONS 3 4.9.13 BORON CONCENTRATION - SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9. 13 The boron concentration in the spent fuel storage pool shall be maintained greater than or equal to 2150 ppm.

APPLICABILITY:

Whenever fuel assemblies are in the spent fuel storage pool.

ACTION:

With the requirements of this specification not satisfied, suspend all movement of fuel assemblies in the spent fuel storage pool and restore the boron concentration to 2150 ppm or greater.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9. 13 The boron concentration of the spent fuel storage pool shall be determined by chemical analysis at least once per 7 days when fuel assemblies are in the spent fuel storage pool.

PALO VERDE UNIT 2 3/4 9-17

.AMENDMENT NO. 69

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BASES A shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8-hour period during surveillance testing of ECCS pumps.

This is necessary to meet Surveillance 4.5.2, flow testing of the HPSI pumps without other pumps

running, and 4.3.3.5, testing of the containment spray pumps and LPSI pumps during surveillance of the remote shutdown system.

3 4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.

The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3 4.9. 10 and 3 4.9. 11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth (at least 23 feet above the top of the spent fuel) is available to remove a nominal 99X of the assumed 10X iodine gap activity released from the rupture of an irradiated fuel assembly for a maximum fuel rod pressurization of 1200 psig.

The minimum water depth is consistent with the assumptions of the safety analysis.

3 4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM The limitations on the fuel building essential ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.

The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) to meet the guidance of Regulatory Guide 1.52, Revision 2, Positions C.6.a and C.6.b, has been found acceptable as documented in Revision 2 to Section 6.5. 1 of the Standard Review Plan (NUREG-0800).

3

.9. 13 BORON CONCENTRATIO SPENT FUEL STORAGE POOL The restriction on the boron concentration of the spent fuel storage pool ensures that k,<< is maintained less than or equal to 0.95 in the event that either a new or spent fuel assembly is either improperly loaded into any available storage location in the spent fuel storage pool, or is dropped in the gap between the pool wall and a Region 3 storage rack.

This boron concentration is more than adequate to ensure that the k << limit of 0.95, delineated in Specification 5.6. 1. l.a, will not be violated.

PALO VERDE - UNIT 2 B 3/4 9-3 AMENDMENT NO. & 69

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I 14 DESIGN FEATURES 5.3 REACTOR CORE FU L ASSEMBLIES 5.3. 1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods consisting of Zircaloy-4 or stainless steel may be made if justified'y a cycle specific reload analysis.

Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approximately 1950 grams uranium.

Each burnable poison rod shall have a nominal active poison length of 136 inches.

The initial core loading shall have a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum radially averaged enrichment of 4.30 weight percent U-235 at any axial location.

CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained:

In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable surveillance requirements, b.

For a pressure of 2500 psia, and C.

For a temperature of 650'F, except for the pressurizer which is 700'F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900

+ 300/-0 cubic feet at a nominal T,, of 593'F.

PALO VERDE UNIT 2 5-5 AMENDMENT NO. 44-,~,

69

DESIGN 'FEATURES a

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5. 5 ETEOROLOG ICAL 'TOh/ER LOCA I'ION 5.5. 1 The meteorological tower shall Ibe located as shown on I;igure 5.1-1.

5 6 FUEL STORAGE 5.6.1 T

A I Y

5.6. 1'. 1 The spent fuel storage racks are desilgndd hnd shall be maintained'ith:

a.

The maximum calculated k,-<<: value, including margin for uncertainty

'n calculational method and mechanical to erances, less than or equal, to 0.95 with-a 95% probability at -a 55k c nfidqnc'e )evel when flood'ed'ith unborated water.

b.

A nominal 9.5 inches center-to-center distance between adjacent storage cell 'locations.

5.6.1.2 The k,<< for. new fue'1 for the first coIre 'lohdi'ng'st'ored dry in the spent fuel storage raicks,shall.not exceed 0.98 when aqueous foam moderation is assumed.

5.6. 1.3 The spent fuel storage pool is organized into three regions for s',pent

'uel storage.

Fuel shall be placed in the appHopt'iite'egion based on appro-priate initial enrichment and existing burnup as idesignated in Figure 5.6-1'.

a.

Region 1:: Fuel slhall be stored in a checkerboard (two-out-of-four} storage pattern.

Fuel that qualifies to be stored in Regions 1, 2, or 3, in accordance with Figure 5.6-1, may be stored in Region l.

b.

Region 2: Fuel shall be stored in a three-out-of-four storag'e pattern.

Fuel that qualifies to be stored in Regions 2 or 3,

.in accordance with Figure 5.6-1, may be stored in Region 2.

c.

Region 3: Fuel shall be stored in a four-out-of-four storage pattern.

Only fuel that qualifies to be stored in Region 3, i~~

accordance with Figure 5.6-1, shall be storedl in Region 3.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the poo'I below elevation 137 feet - 6 inches.

'APACITY 5.6.3 The spent fuel storage pool is designed hand shal'l be maintained wi'th a storage capacity limited to no more than 1329 fidel a4se'mblie's.

5 7 COMPONENT CYCLIC OR TRANSIE'NT LIMI'II'S 5.7. 1 The components identified in Table 5.7-1 are designed and shall be maintained within the cy'clic or transient limits of Tables 5.7-1 and 5a7-2.

PALO VERDE UNIT 2 5-6 AMENDMENT NO. 69

FIGURE 5. 6-1 ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT 50000 4.30

~ 45000

>400OO W 35000 REGION 3

~ 30000 D 25000 CQ 0 20000 E 15000 (D

~+ 10000 REGION 2 REGION 1 5000 0

2.00 2.50 3.00 3.50

.4.00 Initial Enrichment, wt '6 4.50 5;00 aaaaO 4/4

~ee)ce 5/4 PALO VERDE - UNIT 2 5-6a AMENDMENT NO.

69

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No.

NPF-74 The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by the Arizona. Public Service Company (APS or the licensee) on behalf of.itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric

Company, Southern California Edison

Company, Publ,ic Service Company of New Mexico, Los Angeles Department of Water and

Power, and Southern California Public Power Authority dated February 18,

1994, as supplemented by letter dated June 20,

1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

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

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

NPF-74 is hereby amended to read as follows:

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3.

(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 54, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

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

Plan, except where otherwise stated in specific l-icense conditions.

This l.icense amendment is effective as of the. date of issuance and must be fully implemented no later than 45 days from, the date of issuance.

FOR THE NUCL'EAR REGULATORY COMMISSION QA'heodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

September 3O,

)994

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ATTACHMENT TO LICENSE AMENDMENT MENDMENT NO.

54 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.

Remove IX XIV XIX 8 3/4 9-3 5-5 5-6 Insert IX XIV XIX 3/4 9-17 B 3/4 9-3 5-5 5-6 5-6a

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INDEX

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LIMITING CONDITIONS F~.

OPERATION AND SURVEILLANCE RE EMENTS SECTION ELECTRICAL POWER SYSTEMS (Continued) 3/4.8.2 D.C.

SOURCES PERATING..........................................

0 SHUTDOWN...........................................

3/4.8.3 ONSITE POWER DISTRIBUTION SYSTEMS PERATINGo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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3/4.8. 4 ELECTRICAL EQUIPMENT PROTECTIVE 'DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES...............................

MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION AND BYPASS DEVICES...............................

3 4.9 REFUELING OPERATIONS 3/4.9. 1 BORON CONCENTRATION...

3/4.9.2 INSTRUMENTATION............

3/4.9.3 DECAY TIME..............,................................

PAGE 3/4 8-9 3/4 8-13 3/4 8-14 3/4 8-16 3/4 8-17 3/4 8-40 3/4 9-1 3/4 9-2 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.......................

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

3/4.9.6 REFUELING MACHINE.

3/4 9-5 3/4 9-6 3/4.9.7 CRANE TRAVEL SPENT FUEL STORAGE POOL BUILDING.........

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

LOW WATER LEVEL..............................

3/4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM................

3/4.9. 10 WATER LEVEL REACTOR VESSEL FUEL ASSEMBLIES.......

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3/4 9-8 3/4 9-9 3/4 9-10 3/4 9-11 3/4 9-12 3/4 9-13 3/4.9.12 FUEL BUILDING ESSENTIAL VENTILATION SYSTEM..............

3/4 9-14 3/4.9.13 BORON CONCENTRATION SPENT FUEL STORAGE POOL............

3/4 9-17 3 4.10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN AND Kq. )

CEA WORTH TESTS.......

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

3/4. 10.3 REACTOR COOLANT LOOPS........

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

54

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INIDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE R~EUIREMENTS SECTION 3/4. 10. 4 3/4. 10; 5 3/4.3.0. 6 3/4.10.7 3/4. 10. 8 3/4. 10. 9 3/4. 10. 10 CEA POSITION, REGULATING CEA INSERTION LIHIT!S AND REACTOR COOLANT COLD Ll=G TEMPERATURE....,.....

MINIMUM TEMPERATIURE AND PRESSURE FOR 'CRITICALITY.

SAFETY INJECTION TANKS.....,............,......,....

SPENT FUEL POOL ILEVEL.......,............,......,....

SAFETY INJECTION TANK PRESSURE..............,....

SHUTDOWN MARGI,'N AND'N 1 CEDMS TESTING

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NATURAL CIRCULATION TESTING PROGRAM.....,.........

PAGE 3/4 10-4 3/4 10-5 3/4 10-6 3/4 10"7 3/4 10"8 3/4 10-9 3/4 10-10 3/4. 11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID HOLDUP TANKS.....................,............,....

3/4.11.2 EXPLOSIVE GAS MIXTURE..

3/4. 11. 3 GAS STORAGE TANKS............,...........,.............;..

3/4 11 1 3/4 11"2 3/4 ll 3 PALO VERDE - UNIT 3 AMENDMENT NO. 2, 34

BASES INDEX SECTION 3/4.7 PLANT SYSTEMS 3/4. 7. 1 TURBINE CYCLE..............,....

PAGE 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...

3/4 7.6 ESSENTIAL CHILLED WATER SYSTEM.;....

B 3/4 7-4 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..........

3/4.7.9 SNUBBERS.......

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

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, ONSITE POWER DISTRIBUTION SYSTEMS...........

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

B 3/4 8-3 3/4. 9 REFUELING OPERATIONS 3/4.9. 1 BORON CONCENTRATION...

3/4. 9. 2 INSTRUMENTATION.........................................

3/4.9.3 DECAY TIHE..................;...........................

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

B 3/4 9.-1 3/4. 9. 5 COMMUNICATIONS..

3/4. 9. 6 REFUELING MACHINE....................................-...

B 3/4 9-.1 B 3/4 '9-2 PALO VERDE - UNIT 3.

AMENDMENT NO.

2

BASES

~SCT ON IN[)EX PAGE f ~I

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S 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING..........

B 3/4 942 3/4 ~ 9 o 8 SHUTDOWN COOLI NG AND COOI ANT CIRCULATIONe

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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 3/4.9.12 FUEL BUILDING ESSENTIAL'ENTILATION SYSTEM 3/4.9.13 BORON CONCENTRATION SPENT FUEL STORAGE POOL...........

3 4.10 SPECIAL TEST EXCEPTIONS 3/4. 10. 1 SHUTDOWN MARGIN AND Kx,.l CEA WORTH TESttS..'.'...'..'......

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

3/4. 10.3 REACTOR COOLANT LOOPS.....................,.............

3/4.10.4 CEA POSITION, REGULATING CEA INSERTION LIMITS AND REACTOR COOLANT COLD LEiG TEMPERATURE B 3/4 9'3 3/4'-'3 3/4 I()-ll B 3/4I 10-1 B 3/4 10-1 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...,..............................

3/4.10.7 SPENT FUEL POOL LEVEL....,................,.............

B 3/4 10-2 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,.1 CEDMS TESTING 3 4.11 RADIOACTIVE EFFLUEN'TS 3/4.11.1 LIQUID HOLDUP TANKS........................

3/4.11.2 EXPLOSIVE GAS MIXTURE........................

3/4. 11.3 GAS STORAGE TANKS....................,............,......

B 3/4 10-2' 3/4 ll-l

.B 3/4 ll-l B 3/4 ll-l PALO VERDE UNIT 3 XIV AMENDMENT NO. 8, +4-,

54

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'j LIST OF FIGURES INDEX PAGE 3.1-1 3.2-1 3.4-1 3.4-2a 3.4-2b 3.4-2c 3.4-2d MINIMUM BORATED'ATER VOLUMES..........................

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

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

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

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

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

REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE HEATUP AND COOLDOWN RATES FOR',LESS THAN 8 EFPY OF 0 PE RATION ~

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REACTOR COOLANT SYSTEM MAXIMUMALLOWABLE.HEATUP AND COOLDOWN RATES FOR 8 TO 32 EFPY OF PERATION..............................................

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

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

GASEOUS RELEASE POINTS......

ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT...............

5-2 5-3 5-ea SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

3/4 7-26 PALO VERDE UNIT 3 XIX AMENDMENT NO. 88, 42

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LIST OF TABLES 0

INDEX PAGE

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ail 1.2

2. 2-1 FREQUENCY NOTATION.........,........

OPERATIONAL MODES.....,....;.............

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOiNT IMITSo ~ ~ ~ ~ ~

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3. 3-1

3. 3-2

4. 3-1 REACTOR PROTEC1IVIE INSTRUMENTATION SUR'VEILLANCE REQUIREMENTS...........,..................,...............

3/4 3-14 REACTOR PROTECTIVE INSTRUMENTATION.............-.........

3/4 3-3 REACTOR PROTECTIVIE INSI'RUMENTA'TION RESPONSE TIMES.......

3/4 3-11'

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3. 3-4

3. 3"5

4. 3-2

3. 3-6

4. 3-3 3 0 3 7 4.3-4 ENGINEERED SAFETY FEATURES ACTIIjATION SYSTEM INSTRUMENTATIOhl..............

ENGINEERED SAFETY FEATURES ACTIVATION SYSTEM INSTRUMENTATIONI TRIP VALUES..........'...'..'...'..'...'...'...

ENGINEERED SAFETY FEATURES RESPONSE TIMES..............

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATIONI SURVEILLAlkCE RI.QUIREMENTS.....'..........

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

RADIATION MONITORING INSTIRUHENTATION SURVEILLANCE REQUIREMENTS,......,............,......................,..

SEISMIC MONITORING INSTRUI4IENITATION..........'......'...'...'...

SEISMIC MONITORING INSl'RUMENITAI ION SURVEILLANCE

'EQUIREMENTS,..............

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3/4 3-18 3/4

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'/4 3-38 3/4 3-40 3/4 3-43 3/4 3-44

3. 3-8 METEOROLOGICAL MONITORING INISTRUMENTATION..>>............

3/4 3-46 i

4. 3-5 METEOROLOGICAL MONITORING INISTRUMENTATION SURVEILLANCE REQUIREiMEhlTS............ 3.... l..'...'.'...'.

3.3-9B REMOTE SHUTDOWN DISCONhlECT SWITCHES... i.... t..'...'.'...'.

3. 3-'9A.

REMOTE SHUTDOWN INSTRUMENTATION.......<.... I...'...'.'...'.

3/4 3-47 3/4 3-49 3/4 3-50 PALO VERDE - UNIT 3 XX AMENDMENT NO, j(8s 42

H4.9 N~EUELIN PENPTI N

0 3 4.9. 13 BORON CONCENTRATION SPENT FUEL STORAGE POOL LIMITING CONDITION FOR OPERATION 3.9.13 The boron concentration in the spent fuel storage pool shall be maintained greater than or equal to,2150 ppm.

BPPLILNNI LITT tlt f

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P ACTION:

With the requirements of this specification not satisfied, suspend all movement of fuel assemblies in the spent fuel storage pool and restore the boron concentration to 2150 ppm or greater.

The provis'ions of Specification 3.0.3 are not applicable.

SURVEILLANCE RE UIREMENTS 4.9. 13 The boron concentration of the spent fuel storage pool shall be determined by chemical analysis at least once per 7 days when fuel assemblies are in the spent fuel storage pool.

PALO VERDE UNIT 3 3/4 9-17 AMENDMENT NO.

54

C

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~REFUEL LEE FERREI BASES A shutdown cooling loop may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per.

8-hour period during surveillance testing of ECCS pumps.

This is necessary to meet Surveillance 4.5.2, flow testing of the HPSI pumps without other pumps

running, and 4.3.3.5, testing of the containment spray pumps and LPSI pumps during surveillance of the remote shutdown system.

3 4.9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABILITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment.

The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

3 4.9.10 and 3 4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE POOL The restrictions on minimum water level ensure that sufficient water depth (at least 23 feet above the top of the spent fuel) is available to remove a nominal 99X of the assumed IOX iodine gap activity released from the rupture of an irradiated fuel assembly for a maximum fuel rod pressurization of 1200 psig.

The minimum water depth is consistent with the assumptions of the safety analysis.

3 4.9.12 FUEL BUILDING ESSENTIAL VENTILAT ON SYSTEM The limitations on the fuel building essential ventilation system ensure that all radioactive material released from an irradiated fuel assembly will be filtered. through the HEPA filters and charcoal adsorber prior to discharge to the atmosphere.

The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the safety analyses.

The use of ANSI Standard N509 (1980) in lieu of ANSI Standard N509 (1976) to meet the guidance of Regulatory Guide 1.52, Revision 2, Positions C.6.a and C.6.b, has been found acceptable as documented in Revision 2 to Section 6;5. 1 of the Standard Review Plan (NUREG-0800).

3 4.9.13 BORON CONCENTRATION SPENT FUEL STORAGE POO The restriction on the boron concentration of the spent fuel storage pool ensures that k,<< is, maintained less than or equal to 0.95 in the event that either a new or spent fuel assembly is either improperly loaded into any available storage location in the spent fuel storage pool, or is dropped in the gap between the pool wall and a Region 3 storage rack.

This boron concentration is more than adequate to ensure that the k << limit of 0.95, delineated in Specification 5.6. l.l.a, will not be violafed.

PALO VERDE UNIT 3 B 3/4 9-3 AMENDMENT NO. 54

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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods con-sisting of Zircaloy-4 or stainless steel may be made if justified by a cycle specific, reload analysis.

Substitution of up to a total'f 80'uel rods clad with zirconium-based alloys other than Zircaloy-4 may also be made in two fuel assemblies for in-reactor performance evaluation purposes during Cycles 4, 5

and 6.

Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approximately 1950 grams uranium.

Each burnable poison rod shall have a nominal active poison length of 136 inches.

The initial core loading shall have a maximum enrichment of,3.35 weight percent U-235.

Reload fuel shall be simi.lar in physical design to the initial core loading and shall have a maximum radially averaged enrichment of 4.30 weight percent U-235 at any axial location.

CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4. 1 The Reactor Coolant System is designed and shall:be maintained:

a.

In accordance with the code requirements specified in Section 5.2'f the FSAR with allowance for normal degradation pursuant of the applicable surveillance requirements, b.

For a pressure of 2500 psia, and c.

For a temperature of 650'F, except for the pressurizer which is 700'F.

VOLUME 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900

+ 300/-0 cubic feet at a nominal T,, of 593 F.

PALO VERDE UNIT 3 5-5 AMENDMENT NO. 8

, 38, 4&, '54

DESIGN FEATURES

5. 5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located aS shown on Figure 5.1-11 5.6 FUEL STORAGE 5.6.1

- CRITICALITY 5.6. 1. 1 The spent fuel storage racks are designed'and shall be maintained with:

a 0 The maximum calculated k<< value,, including margin for uncertainty'n calculational method and mechanikall tble&ances, 'less than or equal to 0.95 with a 95X probability at al 95X konfidence level when flooded with unborated water.

b.

A nominal 9.5 inches'enter-to-center

'dista'nce between adjacent storage cell locations,.

5.6. 1.2 The k,<< for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation

'is'ssumed.

5.6. 1.3 The spent fuel storage pool is orgahided into 'three regions for spent fuel storage.

Fuel shall be placed in the appropriate region based on appro-priate initial enrichment and ex'isting burnup as designated in Figure 5.6-1:

a.

Region 1: Fuel shall be stored in a checkerboard (two-out-of-four) storage pattern.

Fuel that qualifies to be stored in Regions 1, 2, or 3, in accordance with Figure 5.6-1, may be stored in Region l.

b.

Region,2:

Fuel shall be stored in a three-out-of-four storage pattern.

Fuel that qualifies to be stored in Regions 2 or 3, in accordance with Figure 5.6-1, may be stored in Region 2.,

c.

Region,'3:

Fuel shall be stored in a four-out-of-four storage pattern.

Only fuel that qualifies to be stored in Region 3, in accordance with Figure 5.6-1, shall be stored in Region 3.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shhll'h 5aintaindd to prevent inadvertent draining of the pool below elevation 137 feet - 6 inches.

CAPACITY 5.6.3 The spent fuel storage pool is designed aAd shlall be maintained with a storage capacity limited to no more than 1329'fu'el'assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIFIITS 5.7; 1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Tables 5.7-1 and 5.7-2.

PALO VERDE UNIT 3 5-6 AMENDHENl NO.

54

0 FIGURE 5.6-1 ASSEMBLY BURNUP VERSUS INITIAL ENRICHMENT 50000

'4.30

~ 45000

>4oooo W 35000

~\\

Z 30000

~ 25000 ccj

~20000 E 15000

~+ 10000 5000 REGION 3 REGION 2 REGION. 1 0

2.00 2.50 3.00 3.50 4.00 4.50 Initial Enrichment, wt K 5.00 QQQQD 4/4

~was>c g/4 PALO VERDE UNIT 3 5-6a AMENDMENT NO. 54

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