Text

Amends 38,25 & 14 to Licenses NPF-41,NPF-51 & NPF-74, Respectively,Modifying Tech Specs to Require That Azimuthal Power Tilt Be Equal or Less than Core Protection Calculator
	ML17304A653
Person / Time
Site:	Palo Verde
Issue date:	10/17/1988
From:	Knighton G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML17304A654	List: ML17304A653; ML17304A656;
References
	NUDOCS 8810260446
	Download: ML17304A653 (41)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. O. 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. 38 License No.

NPF-41 1.

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

A.

The application for amendment, dated May 27, 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; B.

The facility will.operate in conformity with the application, the provisions of the Act, and the regulations of the COIImIission; 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 coaaen defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by a change 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:

88i0260446 881017 PDR ADOCK 05000528 P

PDC (2)

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

38

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

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

3.

This license amendment is effective as of the date of issuance.

The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.

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

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications Date of Issuance:

October 17,'988 George W

Knighton, rector Project Directorate V

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

g

~

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ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

38 TO FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

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

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

Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pa e

xix 3/4 2-3 3/4 2-4 3/4 2-4a B3/4 2-2 Overleaf Pa e

xx B3/4 2-1

~

LIST OF FIGURES INDEX PAGE I

3. 1-1A

3. 1-1

3. 1-2

3. 1-2A

3. 1-3

3. 1-4

3. 1-5

3. 2-1A

3. 2-1

3. 2"2

3. 2-2A 3.2 3

3. 4-1

3. 4-2

4. 7-1 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 IN SERVICE).

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 EVELt ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

i ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

L DOSE E(UIVALENT 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..............

SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..........,....

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 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 6.2-1 6.2-2 SITE AND EXCLUSION BOUNDARIES...........................

LOW POPULATION ZONE...

GASEOUS RELEASE POINTS OFFS ITE ORGANIZATION.........................

ONS ITE UNIT ORGANIZATION...............................

5-2 5-3 6-3 PALO VERDE - UNIT 1 XIX AMENDMENT NO.

38

LIST OF TABLES INDEX PAGE 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

3. 3-6

4. 3-3 3.3-7 4.3-4

3. 3-8

4. 3-5

3. 3-9A 3.3-98 FOR K

> 0.98.

eff FOR 0.98 K ff > 0.97..

FOR 0.97 K ff > 0.96.............

FOR 0.96 K

0 95 FOR K re 0 ~ 95

~

REACTOR PROTECTIVE INSTRUHENTATION. ~

~

~ i

~

REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES ~..

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREHENTS...........

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.

ENGINEEREO 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.................................

SEISMIC MONITORING INSTRUHENTATION.........

SEISMIC MONITORING INSTRUHENTATION SURVEILLANCE REQUIREMENTS....

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

METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTS....................

REMOTE SHUTDOWN INSTRUMENTATION.

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

FREQUENCY NOTATION.

OPERATIONAL MODES....

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT IMITSo ~

~

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

POWER DISTRIBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - T LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the q

following limits:

a.

The AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs),

and

b. 1.

The limit in Figure 3.2-1A with COLSS in service, or b.2.

T

< 0. 10 with COLSS out of service.

APPLICABILITY:

MODE 1 above 20K of RATED THERMAL POWER".

ACTION:

b.

With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value.

With the measured AZIMUTHAL POWER TILT determined to exceed the limit in Figure 3.2-1A with COLSS in service or 0. 10 with COLSS out of service:

.l.

Due to misalignment of either a part-length or full-length CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS)

(when COLSS is being used to monitor the core power distribution per Specifications 4.2. 1 and 4.2.4) is detecting the CEA misalignment.

2.

Verify that the AZIMUTHAL POWER TILT is within 'its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the limit or reduce THERMAL POWER to less 'than 50'f RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and verify that the Variable Overpower Trip Setpoint has been reduced as appropriate within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50K of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95X or greater RATED THERMAL POWER.

See Special Test Exception 3. 10.2.

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

38

POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 The AZIMUTHAL POWER TILT shall be determined to be within its limits above 20X of RATED THERMAL POWER by:

'a 0 b.

C.

d.

Continuously monitoring the tilt with COLSS when the COLSS is in service.

Calculating the tilt at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the COLSS is out of service.

Verifying at least once per 31 days, that the COLSS Azimuthal Tilt Alarm is actuated at an AZIMUTHAL POWER TILT less than or equal to the AZIMUTHAL POWER TILT Allowance used in the CPCs.

Using the incore detectors at least once per 31 EFPD to independently confirm the validity of the COLSS calculated AZIMUTHAL POWER TILT.

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

1.0 0.9 R

Z

, 0.8 M

U T

H o

~ 7 Fl L

p 0.6 0

W E

R 0.5 T

. I L O.u T

F R

0 C

T 0.2 I

N 0.1 0.0 20 30 tIO 50 60 70 PERCENT OF RATED THERMAL POWER 80 90 100 FIGURE 3.2 - 1A AZIMUTHAL POWER TILT LIMIT VS THERMAL POWER (COLSS IN SERVICE)

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

A

3/4.2 POWER DISTRIBUTION LIMITS BASES 3/4.2.1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a

LOCA, the peak temperature of the fuel cladding will not exceed 22004F.

Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the Local Power Density channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate does not exceed its limits.

The COLSS performs this function by continuously monitoring the core power distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate.

Reactor operation at or below this calculated power level assures that the limits of 13.5 kW/ft are not exceeded.

The COLSS calculated core power and the COLSS calculated core power operating limits based on linear heat rate are continuously monitored and displayed.to the operator.

A COLSS alarm is annunciated in the event that the core power exceeds the core power opirating limit.

This provides adequate margin to the linear heat rate operating limit for normal steady-state opera-tion.

Normal reactor power transients or equipment failures which do not require a reactor trip may result in this core power operating limit being exceeded.

In the event this occurs, COLSS alarms will be annunciated.

If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the Reactor Protective Instrumentation.

The COLSS calculation of the linear heat rate includes appropriate penalty factors which provide, with a 95/95 probability/

confidence level, that the maximum linear heat rate calculated by COLSS is conservative with respect to the actual maximus linear heat rate existing in the core.

These penalty factors are deteriwined from the uncertainties associated with planar radial peaking measurement, engineering heat flux uncertainty, axial densification, software algorithm modelling, computer processing, rod bow, and core power measurement.

Parameters required to maintain the operating limit power level based on linear heat rate, margin to DNB, and total core power are also monitored by the CPCs.

Therefore, in the event that the COLSS is not being used, operation within the linear heat rate limit can be maintained by utilizing any operable CPC channel.

The above listed uncertainty and penalty factors plus those asso-ciated with the CPC startup test acceptance criteria are also included in the CPCs.

PALO VERDE - UNIT 1 B 3/4 2-1 AMENDMENT NO. 24

POWER DISTRIBUTION LIMITS BASES 3/4. 2. 2 PLANAR RADIAL PEAKING FACTORS Limztzng the va ues of the PLANAR RADIAL PEAKING FACTORS (F

) used in the xy COLSS and CPCs to values equal to or greater than the measured PLANAR RADIAL PEAKING FACTORS (F

) provides assurance that the limits calculated by COLSS xy and the CPCs remain valid.

Data from the incore detectors are used for determining the measured PLANAR RADIAL PEAKING FACTORS.

A minimum core power at 20K of RATED THERMAL POWER is assumed in determining the PLANAR RADIAL PEAKING FACTORS.

The 20K RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20X core power.

Core noise level at low power is too large to obtain usable detector readings.

The periodic surveillance requirements for determining the measured PLANAR RADIAL PEAKING FACTORS provides assurance that the PLANAR RADIAL PEAKING FACTORS used in COLSS and the CPCs remain valid throughout the fuel cycle.

Determining the measured PLANAR RADIAL PEAKING FACTORS after each fuel loading prior to exceeding 70K of RATED THERMAL POWER provides additional assurance that the core was properly loaded.

3/4.2.3 AZIMUTHAL POWER TILT - T The limitations on the AZIMUTHAL POWER TILT are provided to ensure that design safety margins are maintained.

An AZIMUTHAL POWER TILT greater than the limit in Figure 3.2-1A with COLSS in service or 0. 10 with COLSS out of service is not expected and if it should occur, oper ation is restricted to only those conditions required to identify the cause of the tilt.

The tilt is normally calculated by COLSS.

A minimum core power of 20K of RATED THERMAL POWER is assumed by the CPCs in its input to COLSS for calculation of AZIMUTHAL POWER TILT.

The 20'ATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20K core power.

Core noise level at low power is too large to obtain usable detector readings.

The surveillance requirements specified when COLSS is out of service provide an acceptable means of detecting the presence of a steady-state tilt. It is necessary to explicitly account for power asymmetries because the radial peaking factors used in the core power distribution calculations are based on an untilted power distribution.

The AZIMUTHAL POWER TILT is equal to (Pt.lt/P t.lt)-1.0 where:

AZIMUTHALPOWER TILT is measured by assuming that the ratio of the power at any core location in the presence of a tilt to the untilted power at the location is of the form:

tilt untilt 1 + Tq g cos (e - e,)

where:

T is the peak fractional tilt amplitude at the core periphery g is the radial normalizing factor 8 is the azimuthal core location Bo is the azimuthal core location of maximum tilt PALO VERDE - UNIT 1 B 3/4 2-2 AMENDMENT NO. 3B

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UNITEO STATES NUCLEAR REGULATORY COMMISSION WASMINGTON, 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.

25 License No.

NPF-51 1.

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

A.

The application for amendment, dated May 27, 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; B.

The facility will operate in conformity with the application, the provisions of the 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 wi 11 not be inimical to the coaeon 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 a change 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:

f I

L li 8 ~

(2)

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

25

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

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

3.

This license amendment is effective as of the date of issuance.

The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.

In the period between issuance of amendment and the effective date of the new Technical Specifications, the licensees shall adhere to the Technical Specifications existing at the-time.

The period of time during changeover shall be minimized.

FOR THE NUCLEAR REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications Date of Issuance:

October 17,. 1988 George W

Knighton, project irectorate Division of Reactor IV, V and Special

/

erector V

Projects - III, projects

~

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

25 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 area of change.

Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pa e

Overleaf Pa e

3/4 2-3 3/4 2-4 3/4 2-4a B3/4 2-2 xx B3/4 2-1

II

LIST OF FIGURES INOEX

3. 1-lA

3. 1-1

3. 1"2

3. 1-2A

3. 1-3

3. 1-4

3. 1-5

3. 2-1A

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)........

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

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

~

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 EVELt ~

~

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 PERATION ~

~

~ o

~

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 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 B 3/4.4-1

5. 1-1

5. 1-2

5. 1-3 6.2-1 6.2-2 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS A FUNCTION OF FAST (E ) 1 MeV) NEUTRON'LUENCE (550 F IRRADIATION).......................

~ ~...........

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

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

~

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

OFFSITE ORGANIZATION...................................

ONSITE UNIT ORGANIZATION...............................

8 3/4 4-10 5-2 5-3 6-3 6-4 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST..............

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

LIST OF TABLES INDEX PAGE 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

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 IHITSo

~

~ ~

~

~ ~

~

~ ~ ~ ~

~

~ ~ ~ ~ o

~

~ ~

~

~ ~

~

~ ~

~

~ ~ ~ ~

~

~ ~

~

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

OR K ff > 0.98..........................................

F FOR 0.98 K ff > 0.97..................................

FOR 0. 97 K ff > 0.96...............................

~ ~.

FOR 0.96

> K(ff > 0. 95......;...........................

F eff-REACTOR PROTECTIVE INSTRUMENTATION......................

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

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

ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION.........................................

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

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

ENGINEEREO SAFETY FEATURES ACTUATION SYSTEH

'INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............

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

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~

~ ~

~

~ ~

~

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

SEISHIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................

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

METEOROLOGICAL HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................'...............

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

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

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.

POWER DISTRIBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - T q

LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the following limits:

q a.

The AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs),

and

b. l. The limit in Figure 3.2-1A with COLSS in service, or b.2.

T

< 0.10 with COLSS out of service.

APPL!CABIIITY:

MODE 1 above 20K of RATED THERMAL POWER".

ACTION:

With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the'CPCs to greater than or equal to the measured value.

b.

With the measured AZIMUTHAL POWER TILT determined to exceed the limit in Figure 3.2"1A with COLSS in service or 0. 10 with COLSS out of service:

1.

Due to misalignment of either a part-length or full-length CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS)

(when COLSS is being used to monitor the core power. distribution per Specifications 4.2. 1 and 4.2.4) is detecting the CEA misalignment.

2.

Verify that the AZIMUTHAL POWER TILT is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the limit or r'educe THERMAL POWER to less than 50'f RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and verify that the Variable Overpower Trip Setpoint has been reduced as appropriate within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50K of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95K or greater RATED THERMAL POWER.

"See Special Test Exception 3. 10.2.

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

POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4. 2. 3. 2 The AZIMUTHAL POWER TILT shall be determined to be within its limits above 2(C of RATED THERMAL POWER by:

Continuously monitoring the tilt with COLSS when the COLSS is in service.

b.

C.

d.

Calculating the tilt at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the COLSS is out of service.

Verifying at least once per 31 days, that the COLSS Azimuthal Ti 1.t Alarm is actuated at an AZIMUTHAL POWER TILT less than or equal to the AZIMUTHAL POWER TILT Allowance used in the CPCs.

Using the incore detectors at least once per 31 EFPD to independently confirm the validity of the COLSS calculated AZIMUTHAL POWER TILT.

PALO VERDE " UNIT 2 3/4 2-4 AMENDMENT NO. 25

1.0 0.9 A

Z

, 0.8 M

U T

H o ~ 7 A

L P 0.6 6

V E

R 0.5 T

I L O.u T

F R

0 C

T 0.2 I

N 0.1 0.0 20 30 40 50 60 70 PERCENT OF RATED THERMAL POWER 80 90 FIGURE 3.2 - 1A.

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

PALO VERDE - UNIT 2 3/4 2"4a AMENDMENT NO. 25

~

1

~

c

~

3/4.2 POWER OISTRIBU ION LIMITS BASES 3/4. 2. 1 LINEAR HEAT RATE The limitation on linear heat rate ensures that in the event of a

LOCA, the peak temperature of the fuel cladding will not exceed 22004F.

Either of the two core power distribut'ion monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the Local Power Oensity channels in the Core Protection Calculators (CPCs),

provide adequate monitoring of the core power distribution and are capable of verifying that the linear heat rate'oes not exceed its limits.

The COLSS performs this function by continuously monitoring the core power distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate.

Reactor operation at or below this calculated power level assures that the limits of 13.5 kW/ft are not exceeded.

The COLSS calculated core power and the COLSS calculated core power operating limits based on linear heat rate are continuously monitored and displayed to the operator.

A COLSS alarm is annunciated in the event that the core power exceeds the core power operating limit.

This provides adequate margin to the linear heat rate operating limit for normal steady-state opera-tion.

Normal reactor power transients ot equipment failures which do not require a reactor trip may result in this core power operating limit being exceeded.

In the event this occurs, COLSS alarms will be annunciated.

If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the Reactor Protective Instrumentation.

The COLSS calculation of the linear hea't rate includes appropriate penalty factors which provide, with a 95/95 probability/

confidence level, that the maximum linear heat rate calculated by COLSS is conservative with respect to the actual maximum linear heat rate existing in.

the core.

These penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering heat flux uncertainty, axial densification, software algorithm modelling, computer processing, rod bow, and core power measurement.

Parameters required to maintain the operating l.imit power level based on linear heat rate, margin to ONS, and total core power are also monitored by the CPCs.

Therefore', in the event that the COLSS is not being used, operation within the linear-heat rata limit can be maintained by utilizing any operable CPC channel.

The above listed uncertainty and penalty factors plus those asso-ciated with the CPC startup test acceptance criteria are also included in the CPCs.

PALO VEROE - UNIT 2 B 3/4 2-1 AMENOMENT NO.

19

POWER DISTRIBUTION LIMITS BASES 3/4. 2. 2 PLANAR RADIAL PEAKING FACTORS Limiting t e va ues of t e L NA RADIAL PEAKING FACTORS (F

) used in the xy COLSS and CPCs to values equal to or greater than the measured PLANAR RADIAL PEAKING FACTORS (F

) provides assurance that the limits calculated by COLSS and the CPCs remain valid.

Data from the incore detectors are used for determining the measured PLANAR RADIAL PEAKING FACTORS.

A minimum core power at 20K of RATED THERMAL POWER is assumed in determining the PLANAR RADIAI PEAKING FACTORS.

The 20K RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20X core power.

Core noise level at low power is too large to obtain usable detector readings.

The periodic surveillance requirements for determining the measured PLANAR RADIAL PEAKING FACTORS provides assurance that the PLANAR RADIAL PEAKING FACTORS used in COLSS and the CPCs remain valid throughout the fuel cycle.

Determining the measured PLANAR RADIAL PEAKING FACTORS after each fuel loading prior to exceeding 70K of RATED THERMAL POWER provides additional assurance that the core was properly loaded.

3/4.2.3 AZIMUTHAL POWER TILT - T The limitations on the AZIMUTHAL POWER TILT are provided to ensure that design safety margins are maintained.

An AZIMUTHAL POWER TILT greater than the limit in Figure 3.2-1A with COLSS in service or 0.10 with COLSS out of service is not expected and if it should occur, operation is restricted to only those conditions required to identify the cause of the tilt.

The tilt is normally calculated by COLSS.

A minimum core power of 20K of RATED THERMAL POWER is assumed by the CPCs in its input to COLSS for calculation of AZIMUTHAL POWER TILT.

The 20K RATED THERMAL POWER threshold is due to the neutron flux detector system being inaccurate below 20K core power.

Core noise level at low power is too large to obtain usable detector readings.

The surveillance requirements specified when COLSS is out of service provide an acceptable means of detecting the presence of a steady-state tilt. It is necessary to explicitly account for power asymmetries because the radial peaking factors used in the core power distribution calculations are based on an untilted power distribution.

The AZMfTNLPOWER TILT is equal to (P

/P

)-1.0 where:

AZIMUTHALPOWER TILT is measured by assuming that the ratio of the power at any core location in the presence of a tilt to the untilted power at the location is of the form:

+ Tq g cos (e - eo) where:

T is the peak fractional tilt amplitude at the core periphery g is the radial normalizing factor 8 is the azimuthal core location Bo is the azimuthal core location of maximum tilt PALO VERDE - UNIT 2 8 3/4 2"2 AMENDMENT NO. 25

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O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

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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.

14'icense No.

NPF-74'.

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

A.

The application for amendment, dated May 27,

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; B.

The facility will operate in conformity with the application, the provisions of the 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 wi 11 not be inimical to the coaaen defense and secur ity 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 a change 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:

~

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revis'ed through Amendment No.

14

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

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

3.

This license amendment is effective as of the date of issuance.

The changes in the Technical Specifications are to become effective within 30 days of issuance of the amendment.

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

The period of time during changeover shall be minimized.

FOR THE NUCLEAR,REGULATORY COMMISSION

Enclosure:

Changes to the Technical Specifications Date of Issuance:

October 17, 1988 George W

nighton, ector Project Directorate V

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

a

ENCLOSURE TO LICENSE AMENDMENT AMENDMENT NO.

14 'O 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 area of change.

Also to be replaced are the following overleaf pages to the amended pages.

Amendment Pa e

Xix 3/4 2-3 3/4 2-4 3/4 2-4a B3/4 2-2 Overleaf Pa e

XX B3/4 2-1

g

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

3. 2-lA

3. 2",1

3. 2-2

3. 2-3

3. 3-1

3. 4-1

3. 4-2 SHUTDOWN MARGIN VERSUS COLO 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 fVELo ~

~

~ ~ ~

~

~ ~

~

~ ~

~

~ ~

~ ~ ~

~

~ ~

~ o ~ ~

L DNBR MARGIN OPERATING LIMIT BASED ON COLSS FOR BOTH CEAC'S'NOPERABLE.............................

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 0 PERATIONo ~ ~

~ ~

~ ~ ~ ~ ~ ~

~ o

~

~ ~ ~

~

~ ~ ~

~ ~

~

~ ~

~ ~ ~ ~

~

~ ~

~

~ ~

~

~ ~ ~ ~

~ ~

~

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 B 3/4.4-1 NIL-DUCTILITYTRANSITION TEMPERATURE INCREASE AS FUNCTION OF FAST (E > 1 MeV) NEUTRON FLUENCE (5M4F IRRADIATION)..............................

A.

8 3/4 4-10 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST,.............

3/4 7-26

5. 1-1

5. 1-2

5. 1-3 6.2-1 6.2-2 SITE AND EXCLUSION BOUNDARIES..........................

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

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

OFFSITE ORGANIZATION...................................

ONSITE UNIT ORGANIZATION...............................

5-2 5"3 6-3 6-4 PALO VERDE - UNIT 3 XIX AMENDMENT NO. i4

LIST OF TABLES INOEX PAGE 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 3.3-2a

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 FOR Keff )

Oo 98o o

~

~ ~

~ o ~ ~

~

~ o ~ ~

~

~ ~

FOR 0.98 )

K ff ) 0.97.............

FOR 0 97 )

K ff ) 0 96 FOR 0.96 ) K~ff ) 0.95.............

FOR K ff < Oo95o

~

~ ~ ~

~

~ ~ ~

~

~ ~ ~ ~ ~ ~ ~

REACTOR PROTECTIVE INSTRUHENTATION.

REACTOR PROTECTIVE INSTRUMENTATION

~ ~ ~

~

~ ~ ~ ~

~ ~ ~

~

~ ~

~

~ ~

~ ~ ~

~

RESPONSE TIMES.......

INCREASES IN BERRO,

BERR2, AND BERR4 VERSUS RTD DELAY TIHESo o ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREHENTS..........................................

ENGINEERED SAFETY FEATURES ACTUATION SYSTEH 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 REQUIREMENTSo ~ ~ ~ o ~ ~ ~

~

~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~

~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~

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

SEISHIC MONITORING INSTRUMENTATION SURVEILLANCE REQ UIREHENT5 o ~ ~ ~ ~

~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

~

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

HETEOROLOGICAL HONITORING INSTRUMENTATION...............

METEOROLOGICAL HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS...............................

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

REHOTE SHUTDOWN DISCONNECT SWITCHES.....................

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

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

REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT IMITS~ ~

~ ~ ~

~ ~

~

~ ~ o

~

~ o

~

~ ~ ~ ~ ~ ~ ~ ~

~ ~

~

~ ~ ~ ~

~ ~

~

~ ~ ~

~

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

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

POWER DISTRIBUTION LIMITS 3/4.2.3 AZIMUTHAL POWER TILT - T q

)

LIMITING CONDITION FOR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the following limits:

q a.

The AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs),

and

b. l. The limit in Figure 3.2-1A with COLSS in service, or b.2.

T

< 0. 10 with COLSS out of service.

APPLICABILITY:

MODE 1 above 20K of RATED THERMAL POWER*.

ACTION:

a.

With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either correct. the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used'in the CPCs to greater than or equal to the measured value.

b.

With the measured AZIMUTHAL POWER TILT determined to exceed the limit in Figure 3.2-1A with COLSS in service or 0. 10 with COLSS out of service.

1.

Due to misalignment of either a part-length or full-length CEA, within 30 minutes verify that the Core Operating Limit Supervisory System (COLSS)

(when COLSS is being used to monitor the core power. distribution per Specifications 4.2. 1 and 4.2.4) is detecting the CEA misalignment.

2.

Verify that the AZIMUTHAL POWER TILT is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the limit or reduce THERMAL POWER to less than 50X of RATED'THERMAL POWER within the, next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and verify that the Variable Overpower Trip Setpoint has been reduced as appropriate within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50K of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until'.verified acceptable at 95K or greater RATED THERMAL POWER.

See Special Test Exception 3. 10.2.

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

14

4 POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 The AZIMUTHAL POWER TILT shall be determined to be within its limits above 20K of RATED THERMAL POWER by:

b.

C.

d.

Continuously monitoring the tilt with COLSS when the COLSS is in service.

I Calculating the tilt at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the COLSS is out of service.

Verifying at least once per 31 days, that the COLSS Azimuthal Tilt Alarm is actuated at an AZIMUTHAL POWER TILT less than or equal to the AZIMUTHAL POWER TILT Allowance used in the CPCs.

Using the incore detectors at least once per 31 EFPD to independently confirm the validity of the COLSS calculated AZIMUTHAL POWER TILT.

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

>4

1.0 0.9 A

Z

, O.e M

U T

H o ~ 7 R

L p 0.6 0

E R 0.5 T

I L O.u T

F R

0 C

T 0.2 I

N 0.1 0.0 20 30 40 SO 60 70 PERCENT OF RRTED THERNAL POWER 80 100 FIGURE 3.2-1A AZIMUTHAL POWER TILT LIMIT VS THERMAL POWER (COLSS IN SERVICE)

PALO VERDE - UNIT 3 3/4 2-4a AMENDMENT NO. >4

I~

l I

I

3/4.2

'POWER DISTRIBUTION LIMITS BASES 3/4.2. I LINEAR-HEAT RATE The limitation on linear heat rate ensures that in the event of a

LOCA, the peak temperature of the fuel cladding will not exceed 2200'F.

Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the Local Power Density channels in the Core Protection Calculators (CPCs), provide adequate monitoring of the core'ower distribution and are capable of verifying that the linear heat rate does not exceed its limits.

The COLSS performs this function by continuously monitoring the core power distribution and calculating a core power operating limit corresponding to the allowable peak linear heat rate.

Reactor operation at or below this calculated power level assures that the limits of 14.0 kW/ft are not. exceeded.

The COLSS c~l.ulated core power and the COLSS calculated core power operating limits based on linear heat rate are continuously monitored and displayed to the operator.

A COLSS alarm is annunciated in the event that the core power exceeds the core power operating limit.

This provides adequate margin to the linear heat rate operating limit for normal steady-state opera-tion.

Normal reactor power ~ransients or equipment failures which do not require a reactor trip may result in this core power operating 1imit being exceeded.

In the event this occurs, COLSS alarms will be annunciated.

If the event which causes the COLSS limit to be exceeded results in conditions which approach the core safety limits, a reactor trip will be initiated by the Reactor Protective Instrumentation.

The COLSS calculation of the linear heat rate

,includes appropriate penalty factors which provide, with a 95/95 probability/

confidence level, that the maximum linear heat rate calculated by COLSS is conservative with respect to the actual maximum linear heat rate existing in the core.

These penalty factors are determined from the uncertainties associated with planar radial peaking measurement, engineering heat flux uncertainty, axial densification, software algorithm modelling, colaputer processing, rod bow, and core power measurement.

Parameters required to maintain the operating limit power level based on linear heat rate, margin to DNB, and total core power are also monitored by the CPCs (assuming minimum core power of 20K of RATED THERMAL POWER).

The 20X RATED THERMAL POMER threshold is due to the neutron flux detector system being inaccurate below 20K core power.

Core noise level at low power is too large to obtain usable detector readings.

Therefore, in the event that the COLSS is not being used, operation within the limits of Figure 3.2-2 can be maintained by utilizing a predetermined local power density margin and a total core power limit in the CPC trip channels.

The above listed uncertainty and penalty factors plus those associated with the CPC startup test acceptance criteria are also included in the CPCs.

PALO VERDE - UNIT 3 B 3/4 2-1

POWER DISTRIBUTION LIMITS BASES 3/4.2.2 PLANAR RADIAL PEAKING FACTORS smut>ng t e va ues o t e RADIAL PEAKING FACTORS (F