ML17304A680

Amends 40,27 & 16 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Deleting Organization Charts from Tech Specs in Accordance W/Generic Ltr 88-06, Removal of Organization Charts from Tech Spec Administrative Control Requirements

ML17304A680
Person / Time
Site:	Palo Verde
Issue date:	10/25/1988
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML17304A681	List: ML17304A680 ML17304A682
References
GL-88-06, GL-88-6, NUDOCS 8811030188
Download: ML17304A680 (48)

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ARIZONA PUBLIC SERVICE COMPANY, ET AL.

DOCKET NO.

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

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

4O License No. NPF-41 1.

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

A.

The application for amendment, dated August 25, 1988, as sup-plemented by letter dated October 18, 1988, 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 Mater and Power, and Southern California Public Power Au-thority (licensees),

complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Comission' regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of Act, and the 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; 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 enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:

Ssii030i88 SSi025 PDR ADOCK 0500052S P

PDC

O

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 40, 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.

FOR THE NUCLEAR REGULATORY COMMISSION George

. Knigh, Director Project Directorate V

Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

Changes to the Technical Specifications Date of Issuance:

October 25, 1988

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 4O 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 lines indicting the areas of change.

REMOVE XVI XIX 6-1 6-3 6-4 INSERT XVI X IX 6-1 6-1A 6-2' 6-3 6-4 The following corresponding overleaf pages are also provided:

XV XX

• Page 6-2 reissued without change

(<

INDEX DESIGN FEATURES SECTION PAGE

'.1 SITE 5.1.1 5.1.2 5.1.3 SITE AND EXCLUSION'OUNDARIES...........................

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

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

5-1 5-1

5. 2 CONTAINMENT 5.2.1 5.2.2 CONFIGURATION...........................................

DESIGN PRESSURE AND TEMPERATURE.............

5-1 5-1 5.3 REACTOR CORE 5.3.1 5.3.2 FUEL ASSEMBLIES.................................;.......

CONTROL ELEMENT ASSEMBLIES..............................

5-5 5-5

,5.4 REACTOR COOLANT SYSTEM 5.4.1 5.4.2 DESIGN PRESSURE AND TEMPERATURE.........................

0 LUMEo

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V 5-5 5-5

5. 5 METEORLOGICAL TOWER LOCATION.................................

5-6 5.6 FUEL STORAGE 5.6.1 5.6.2 5.6.3 CRITICALITY..'...........................................

5-6 0RAINAGE..............................-.................

CAPACITY................................................

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT..........................

5-6 PALO VERDE - UNIT 1" XV

INDEX ADMINISTRATIVECONTROLS SECTION PAGE 6.1 RESPONSIBILITY..............................................

6"1

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE 6-1 6.2.2 UNIT STAFF............

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6"1 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION ~

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6-6 OMPOSITIONo

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C RESPONSIBILITIES...........................

6-6 6-6 AUTHORITY........................

6-6 ECORDS ~ ~

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R 6.2. 4 SHIFT TECHNICAL ADVISOR................................

6-6

6. 3 UNIT STAFF UALIFICATIONS

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6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW BOARD (PRB)

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6-7 COMPOS ITION~

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MEETING FREQUENCY....

QUORUM......

RESPONSIBILITIES.....

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6-8 AUTHORITY.

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RECORDS............

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6-8 6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES....................

6-9 PALO VERDE - UNIT 1 XVI AMENDMENT NO. 4O

LIST OF FIGURES INOEX PAGE 3.1-1A

3. 1-1

3. 1"2

3. 1-2A

3. 1-3

3. 1"4

3. 1-5

3. 2-lA 30 2 1 3.2 2

3.2-2A 3.2-3 3.4-1

3. 4-2 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE..........

ALLOWABLE MTC MODES 1 AND 2..........................

MINIMUM BORATED WATER VOLUMES........................

CORE POWER LIMIT AFTER CEA DEVIATION.................

CEA INSERTION LIMITS VS THERMAL POWER (COLSS IN SERVICE)...................................

CEA INSERTION LIMITS VS THERMAL POWER (COLSS OUT OF SERVICE).....;....-.....................

PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER;....

AZIMUTHAL POWER TILT LIMIT VS THERMAL POWER (COLSS INSERVICE)....................................

COLSS DNBR POWER OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE.....................................

DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE).....

DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs INOPERABLE)...

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

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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 0 TO 10 YEARS OF FULL POWER OPERATION..............

3/4 1-2a 3/4 1-5 3/4 1-12 3/4 1-24 3/4 1-31 3/4 1-32 3/4 1-34 3/4 2-4a 3/4 2-6 3/4 2-7 3/4 2-7a 3/4 2-10 3/4 4-27 3/4 4-29

4. 7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

3/4 7-26 8 3/4.4-1 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E > 1 MeV) NEUTRON FLUENCE (550 F IRRADIATION)....................................

B 3/4 4-10

5. 1-1

5. 1-2

5. 1-3 SITE AND EXCLUSION BOUNDARIES..........;...............

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

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

5-2 5-3 5-4 PALO VERDE - UNIT 1 XIX AMENDMENT NO. 40

LIST OF TABLES ZNOEX 1 ~ 2

2. 2-1

3. 1"1

3. 1-2

3. 1-3

3. 1-4

3. 1-5

3. 3-1 3 ~ 3 2

4. 3-1 3113

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. 3-98 FREQUENCY NOTATION....................

OPERATIONAL MODES~................

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS.

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REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUHPS AND PLANT OPERATIONAL MODES.....

FOR K

> 0.98......

eif FOR 0+98 >

K ff > 0+97

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FOR 0.97 K

> 0.96....

FOR 0.96 K ff > 0.95......-......

FOR K ff < 0.95......

REACTOR PROTECTIVE INSTRUMENTATION.

REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS....................

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ENGINEERED SAFETY FEATURES

RESPONSE

TIMES ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS RADIATION MONITORING INSTRUMENTATION.

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................

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SEISMIC MONITORING INSTRUMENTATION......................

SEISHIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.....

METEOROLOGICAL MONITORING INSTRUMENTATION.........

METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............

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

REMOTE SHUTDOWN DISCONNECT SWITCHES...........

PAGE 1-8 1-9 2-,3 3/4 1-16 3/4 1-17

. 3/4 1-18 3/4 1-19 3/4 1"20 3/4 3-3 3/4 3-11 3/4 3-14 3/4 3-18 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"46-3/4 3-47 3/4 3"49 3/4 3-50 PALO VERDE - UNIT 1 XX AMENDMENT NO.

27

ADMINISTRATIVE CONTROLS

6. 1

.RESPONSIBILITY

6. 1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor, or during his absence from the Control

Room, a

designated individual per Table 6.2-1, shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall be established for unit operation and corporate management.

The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.

Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b.

There shall be an individual executive position (Executive Vice

. President ANPP) in the offsite organization having corporate respon-sibility for overall plant nuclear safety.

This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.

c.

There shall be individual management positions (Plant Managers) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.

d.

Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

6.2.2 UNIT STAFF a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

PALO VERDE - UNIT j.

6-1 AMENDMENT NO.

4O

V ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

C.

d.

e.

6.2.2.1 At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.

In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

A radiation protection technician" shall be onsite when fuel is in the reactor.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Team of at least five members shall be maintained onsite at all times*.

The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.

The unit staff working hours shall be as follows:

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions;

e. g., Senior Reactor Operators, Reactor Operators, radiation protec-tion technicians, auxiliary operators, and key maintenance personnel.

"The radiation protection technician and Fire Team compositi.on may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected

absence, provided immediate action is taken to fill the required positions.

PALO VERDE - UNIT 1 6-la AMENDMENT NO. 4O

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of Shutdown for re-fueling, major maintenance, or.major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):

1)

An individuah should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2)

An individual should not be permitted to work more. than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour

period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period,.all excluding shift turnover time.

3)

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work periods, including shift turnover time.

4)

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

C.

Any deviation from the above guidelines shall be authorized by the Assistant Vice President-Nuclear Production Support, Director, Standards and Technical Support or the Plant Manager or their designees who are

'at the manager level or above, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime in their respective groups shall be reviewed monthly by these authorized indiViduals or their designees to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

PALO VERDE - UNIT 1 6-2 AMENDMENT NO.

25

[THIS PAGE INTENTIONALLYDELETEDj PALO VERDE -)UNIT 1 6-3 AMENDMENT NO. 40

[THIS PAGE INTENTIONALLYDELETED]

PALO VERDE - UNIT 1 AMENDMENT NO.

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 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.

27 License No. NPF-51 1.

The Nuclear Regulatory Commission (the COIrmission) has found that:

A.

The application for amendment, dated August 25,

1988, as supple-mented by 'letter dated October 18,

1988, 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 Power, 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 Commission's regulations set forth in 10 CFR Chapter I; 2.

B.

The facility will operate in conformity with the. application, the provisions of Act, and the 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; 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 enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:

1

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, 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.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Speci ficati ons Date of Issuance:

October 25, 1988 George

Knighton, rector Project Directorate V

Division of Reactor Projects - III, IV, V and Special Projects

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO. 27 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 indicting the areas of change.

RENQVE XVI XIX 6-1 6-3 6-4 INSERT XVI XIX 6>>1 6-lA 2*

6-3 6-4 The following corresponding overleaf pages are also provided:

XV XX

• Page 6-2 reissued without change

INDEX DESIGN FEATURES SECTION PAGE

5. 1 SITE 5.1.1 SITE AND EXCLUSION BOUNDARIES.............

5"1 5.1.2 LOM POPULATION ZONE..........................;..........'.1.3 GASEOUS RELEASE POINTS...................................

5. 2 CONTAINMENT 5-1 5-1 5.2.1 5.2.2 CONFIGURATIONo ~ o ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~

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DESIGN PRESSURE AND TEMPERATURE.........................

5-1

5. 3 REACTOR CORE 5.3. 1 FUEL ASSEMBLIES.........................................

5"5 5.3. 2 CONTROL ELEMENT ASSEMBLIES..............................

5-5 5.4-REACTOR COOLANT SYSTEM 5.4.1 5.4.2 DESIGN PRESSURE AND TEMPERATURE.........................

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V 5-5 5"5

5. 5 METEORLOGICAL TONER LOCATION.................................

5"6

5. 6 FUEL STORAGE 5.6.1 5.6.2 5.6.3 RITICALITYo~

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C 5-6 5-6 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT..........................

5-6 PALO VERDE - UNIT 2 XV

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY...............................................

6"1

6. 2 ORGANIZATION

6. 2. 1 OFFSITE AND ONSITE..............

6-1

6. 2. 2 UNIT STAFF..............

6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION.......

6-6 OMPOS ITIONo

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C RESPONSIBILITIES........................

6-6 UTH0 RITYo

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6. 2. 4 SHIFT TECHNICAL ADVISOR.................

6-6

6. 3 UNIT STAFF VALIFICATIONS....................................

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6-8 RECORDS 6-8

6. 5. 2 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6-9 PALO VERDE - UNIT 2 XVI AMENDMENT NO.

27

LIST OF FIGURES INOEX

3. 1-1A

3. 1-1

3. 1-2

3. 1-2A

3. 1-3

3. 1-4

3. 2-1A

3. 1-5 3.2 1

3. 2-2

3. 2-2A 3.2-3

3. 4-1

3. 4-2 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE............

ALLOWABLE MTC MODES 1 AND 2..........

MINIMUM BORATED WATER VOLUMES..........................

CORE POWER LIMIT AFTER CEA DEVIATION...................

CEA INSERTION LIMITS VS THERMAL POWER (COLSS IN SERVICE)...................

CEA INSERTION LIMITS VS THERMAL POWER (COLSS OUT OF SERVICE).................

AZIMUTHAL POWER TILT LIMIT VS THERMAL POWER (COLSS IN SERVICE)........................,.............

PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER.......

COLSS DNBR POWER OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE.........;.............................

DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs OPERABLE).....

DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEACs INOPERABLE)...

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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 0 TO 10 YEARS OF FULL POWER 0 P ERATI0 N ~

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PAGE 3/4 1-2a 3/4 1-5 3/4 1"12 3/4 1-24 3/4 1-31 3/4 1"32 3/4 2-4a 3/4 1-34 3/4 2-6 3/4 2-7 3/4 2-7a 3/4 2-10 3/4 4-27 3/4 4-29 4.7-1 B 3/4.4-1

5. 1-1

5. 1-2

5. 1-3 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E > 1 MeV) NEUTRON FLUENCE (550 F IRRADIATION)....................................

SITE AND EXCLUSION BOUNDARIES..............

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

GASEOUS RELEASE POINTS.

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3/4 7-26 PALO VERDE - UNIT 2 XIX AMENDMENT NO. 27

LIST OF TABLES gl INOEX I

1.2

2. 2-1

3. 1-1

3. 1-2

3. 1-3

3. 1-4

3. 1-5

3. 3-1 3.3 2

4. 3-1 3 ~ 3 3

3. 3-4

3. 3-5

4. 3-2

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4. 3-3

3. 3-7

4. 3-4

3. 3-8

4. 3-5

3. 3-9A 3.3-9B FREQUENCY NOTATION.......................................

OPERATIONAL MODES.......................................

REACTOR PROTECTIVE INSTRUHENTATION TRIP SETPOINT IMITSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o

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L REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES.....................

FOR K f) > 0.98..........................................

FOR Oo 98 K ff >

Oo 97o

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FOR 0 97 )

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REACTOR PROTECTIVE INSTRUMENTATION......................

REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES.......

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE

'EQUIREMENTS......................'......................

ENGINEERfD SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION.........................................

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES.............................

ENGINEERED SAFETY FEATURES RESPONSE TIMfS...............

ENGINEERED 'SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIRfHENTS...............

RADIATION HONITORING INSTRUMENTATION....................

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS....'........................................

SEISMIC HONITORING INSTRUMENTATION......................

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METfOROLOGICAL HONITORING INSTRUMENTATION.....;.........

METEOROLOGICAL HONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTS.............. -........... "...

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

REMOTE SHUTDOWN DISCONNECT SWITCHES.....................

PAGE 1-8 1-9 2-3 3/4 1-16 3/4 1"17 3/4 1-18 3/4 1-19 3/4 1-20 3/4 3-3 3/4 3-11 3/4 3-14 3/4 3"18 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 3/4 3-47 3/4 3-49 3/4 3-50 PALO VERDE - UNIT 2 XX AMENDMENT NO.

ADMINISTRATIVE CONTROLS 6.1

'RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6. 1.2 The Shift Supervisor, or during his absence from the Control

Room, a

designated individual per Table 6. 2-1, shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION 6.2.1'FFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall be established for unit operation and corporate management.

The offsite and onsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.

Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b.

There shall be an individual executive position (Executive Vice President ANPP) in the offsite organization having corporate respon-sibility for overall plant nuclear safety.

This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.

c.

There shall be individual management positions (Plant Managers) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.

d.

Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

6. 2.2 UNIT STAFF a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.

In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.

PALO VERDE - UNIT 2 6"1 AMENDMENT NO. 27

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

C.

A radiation protection technician" shall be onsite when fuel is in the reactor.

d.

e.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Team of at least five members shall be maintained onsite at all times".

The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other members of the minimum shift crew necessary for safe shutdown of the unit and any. personnel required for other essential functions during a fire emergency.

6.2.2.1 The unit staff working hours shall be as follows:

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g.,

Senior Reactor Operators, Reactor Operators, radiation protec-tion technicians, auxiliary operators, and key maintenance personnel.

• The radiation protection technician and Fire Team composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected

absence, provided immediate action is taken to fill the required positions.

PALO VERDE - UNIT 2 6-la AMENDMENT NO. 27

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating..

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):

1)

~

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2)

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all-excluding shift turnover time.

3)

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work

periods, including shift turnover time.

C.

4)

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the

- entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Assistant Vice President-Nuclear Production Support, Director, Stan-dards and Technical Support or the Plant Manager or their designees who are at the manager level or above, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

Controls shall be included in the procedures such that individual overtime in their respective groups shall be reviewed monthly by these authorized individuals or their designees to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

PALO VERDE - UNIT 2 6-2 AMENDMENT NO.

14

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PALO VERDE - UNIT 2 AMENDMENT NO.

[THIS PAGE INTENTIONALLYDELETED]

PALO VERDE " UNIT 2 6"4 AMENDMENT NO.

27

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+>>*++

UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 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.

16 License No. NPF-74 1.

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

A.

The application for amendment, dated August 25, 1988, as supple-mented by letter dated October 18,

1988, 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 Egison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, 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 Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of Act, and the 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; 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 enclosure to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-74 is hereby amended to read as follows:

'I

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(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A; as revised through Amendment No. 16, 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.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications George W

nighton, rector Pro'ect Directorate Division of Reactor Projects - III, IV, V and Special Projects Date of Issuance:

October 25, 1988

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

16 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 ate identified by Amendment number and contain vertical lines indicting the areas of change.

RENOVE XVI XIX 6-1 6-3 6-4 INSERT XVI X IX 6<<1 6-1A 2*

6-3 6-4 The following corresponding overleaf pages are also provided:

XV XX

• Page 6-2 reissued without change

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INDEX DESIGN FEATURES SECTION PAGE

5. 1'ITE 5.1.1 SITE AND EXCLUSION BOUNDARIES...........................

5-1 5.1.2 LOW POPULATION ZONE......,..............................

5-1 5.1.3 GASEOUS RELEASE POINTS...................................

5-1

5. 2 CONTAINMENT 5.2.1 CONFIGURATION.........................................

5-1

5. 2.2 DESIGN PRESSURE AND TEHPERATURE.........................

5-1 5.3 REACTOR CORE 5.3.1 5:3.2 FUEL ASSEMBLIES......................

5-5 CONTROL ELEMENT ASSEMBLIES..............................

5-5 5A REACTOR COOLANT SYSTEH-5.4.1 5.4.2 DESIGN PRESSURE AND TEMPERATURE.........................

5-5 V0 LUHEo

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5-6

5. 6 FUEL STORAGE

5. 6.1 5.6.2 5.6.3 CRITICALITY..........................

RAINAGE.................-...............

0 APACITY................................................

C 5-6 5-6 5"6 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT...........................

5-6 PNQ VERDE - UNIT 3

INDEX ADMINISTRATIVE CONTROLS SECTION

6. 1 RESPONSIBILITY.

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6. 2 ORGANIZATION 6.2. 1 OFFSITE AND ONSITE............;...................

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6"1 6.2.2 UNIT STAFF.....

6. 2. 3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION.

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6"6 UTHORITY...........

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6. 3 UNIT STAFF UALIFICATIONS.........~.......................,...

6-6 6 ~ 4 TRAINING~

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QUORUM.................

RESPONSIBILITIES.............

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R 6-8 6.5.2 TECHNICAL REVIEW AND CONTROL ACTIVITIES.

6-9 PALO VERDE - UNIT 3 XVI AMENDMENT NO. 16

c LIST OF FIGURES INDEX

3. 1-lA

3. 1-1

3. 1-2

3. 1-2A

3. 1-2B 3 ~ 1 3 3.

1-4'.

2-1A

3. 2"1

3. 2-2 3 ~ 2 3

3. 3M

3. 4-1

3. 4-2 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE............

ALLOWABLE MTC MODES 1 AND 2....................

MINIMUM BORATED WATER VOLUMES..........................

PART LENGTH CEA INSERTION LIMIT VS THERMAL POWER.......

CORE POWER LIMIT AFTER CEA DEVIATION...................

CEA INSERTION LIMITS VS THERMAL POWER (COLSS IN SERVICE)....................:................

CEA INSERTION LIMITS VS THERMAL POWER (COLSS OUT OF SERVICE).................................

AZIMUTHAL POWER TILT LIMIT VS.

THERMAL POWER (COLSS IN SERVICE).....................................

DNBR MARGIN OPERATING LIMIT BASED ON COLSS (COLSS IN SERVICE).....................................

DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATOR (COLSS OUT OF SERVICE)......................

REACTOR COOLANT COLD LEG TEMPERATURE VS CORE POWER LEVELt ~

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

REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR 0 TO 10 YEARS OF FULL POWER PERATION..............................

0 PAGE 3/4 1-2a 3/4 1-5 3/4 1-12 3/4 1"23 3/4 1"24 3/4 1-31 3/4 1-32 3/4 2-4a 3/4 2-6 3/4 2-7 3/4 2-10 3/4 3-10 3/4 4-27 3/4 4"29 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

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

B 3/4 4-10

5. 1-1 5.1-2 5.1-3 SITE AND EXCLUSION BOUNDARIES..........................

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

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

5"2 5"3 PALO VERDE " UNIT 3 XIX AMENDMENT NO. 16

LIST OF TABLES INDEX 1;2

2. 2-1

3. 1-1

3. 1-2

3. 1-3

3. 1-4 3.1-5

3. 3-1

3. 3-2 3o 3 28 4.Fi 3o 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 FOR K f) > 0.98....................

FOR 0.98 K ~~ > 0.97.............

FOR 0 97 K ff >

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REACTOR PROTECTIVE INSTRUMENTATION.

REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIHES.......

INCREASES IN BERRO,

BERR2, AND BERR4 VERSUS RTD DELAY TIMES...........................................

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS..............................o...........

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION..............;.........................

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES...........................

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

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREHENTS.............

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

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTSo

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SEISMIC MONITORING INSTRUMENTATION...............,....

SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE R EQUIREHENTSo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~

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METEOROLOGICAL HONITORING INSTRUMENTATION.............

METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................

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

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REMOTE SHUTDOWN DISCONNECT SMITCHES... ".. ".--.........

FREQUENCY NOTATION......................................

OPERATIONAL NODES.......................................

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT IMITSo ~

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L REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES PAGE 1-8 1"9 2-3 3/4 1"16..

3/4 1-17 3/4 1-18 3/4 1-19 3/4 1-20 3/4 3-3 3/4 3-11 3/4 3-13 3/4 3-14 3/4 3-18 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 3/4 3-47 3/4 3-49 3/4 3-50 PALO VERDE - UNIT 3 XX

ADMINISTRATIVE CONTROLS

6. 1 'RESPONSIBILITY 6.1. 1 The Plant Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor, or during his absence from the Control

Room, a

'esignated individual per Table 6.2-1, shall be responsible for the Control Room command function.

A management directive to this effect, signed by the Vice President-Nuclear Production shall be reissued to all station personnel on an annual basis.

6. 2 ORGANIZATION 6.2.1 OFFSITE AND ONSITE ORGANIZATIONS An offsite and an onsite organization shall be established for unit operation and corporate management.

The offsite and onsite organization shall include the positions for activ'ities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions.

Those relationships shall be documented an) updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the FSAR and updated in accordance with 10 CFR 50.71(e).

b.

There shall be an individual executive position (Executive Vice President ANPP) in the offsite organization having corporate respon-sibility for overall plant nuclear safety.

This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining and providing technical support in the plant so that continued nuclear safety is assured.

c.

There shall be'ndividual management positions (Plant Managers) in the onsite organization having responsibility for overall unit safe operation and having control over those onsite resources necessary for safe operation and maintenance of the plant.

d.

Although the individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

6.2.2 UNIT STAFF a.

Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

PALO VERDE - UNIT 3 6-1 AMENDMENT NO. 16

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

At least one licensed Reactor Operator shall be in the Control Room when fuel is in the reactor.

In addition, while the reactor is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator shal.l be in the Control. Room.

C.

A radiation protection technician" shall be onsite when fuel is in the reactor.

d.

e.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

A site Fire Team of at least five members shall be maintained onsite at all times".

The Fire Team shall not include the Shift Supervisor, the STA, nor the 3 other members of the minimum shift crew necessary for safe shutdown of'the unit and any personnel required for other essential functions during a fire emergency.

6.2.2.1 The unit staff working hours shall be as follows:

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions;

e. g., Senior Reactor. Operators, Reactor Operators, radiation protec-tion technicians, auxiliary operators, and key maintenance personnel.

"The radiation protection technician and Fire Team composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected

absence, provided immediate action is taken to fill the required positions.

PALO VERDE " UNIT 3 6-la AMENDMENT NO. 16

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) b.

Adequate shift coverage shall be maintained without routine heavy use of overtime.

The objective shall be to have operating personnel work a nominal 40-hour week while the plant is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for re-fueling, major maintenance, or major plant modifications, on a tem-porary basis, the following guidelines shall be followed (this ex-cludes the STA working hours):

2) 3)

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />

straight, excluding shift turnover time.

An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour

period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all

,excluding shift turnover time.

A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed between work

periods, including shift turnover time.

C.

4)

Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Assistant Vice President-Nuclear Production Support, Director, Standards and Technical Support or the Plant Manager or their de-signees who are at the manager level or above, or higher levels of management, in accordance with established procedures and with docu-mentation of the basis for granting the deviation.

Controls shall be..

included in the procedures such that individual overtime in their respective groups shall be reviewed monthly by these authorized in-dividuals or their designees to assure that excessive hours have not been assigned.

Routine deviation from the above guidelines is not authorized.

PALO VERDE - UNIT 3 6"2

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[T(IS PAGE INTENTIONALLYDELETEDI PALO VERDE - UNIT 3 6-3

'I AMENDMENT NO. 16

[THIS PAGE INTENTIONALLYDELETEDj PALO VERDE - UNIT 3 6-4 AMENDMENT NO. 16