ML040850316

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Technical Specification Pages for Amendment Nos. 152, 152 an 152, Palo Verde Nuclear Generating Station, Units 1, 2 and 3
ML040850316
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 03/23/2004
From: Fields M
NRC/NRR/DLPM/LPD4
To: Overbeck G
Arizona Public Service Co
Fields M B ,NRR/DLPM,415-3062
Shared Package
ML040860597 List:
References
TAC MC0870, TAC MC0871, TAC MC0872
Download: ML040850316 (18)
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PALO VERDE NUCLEAR GENERATING STATION IMPROVED TECHNICAL SPECIFICATIONS TABLE OF CONTENTS 1.0 USE AND APPLICATION 1.1 Definitions 1.2 Logical Connectors 1.3 Completion Times 1.4 Frequency 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.2 SL Violations 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) -- Reactor Trip Breakers Open 3.1.2 SHUTDOWN MARGIN (SDM) -- Reactor Trip Breakers Closed 3.1.3 Reactivity Balance 3.1.4 Moderator Temperature Coefficient (MTC) 3.1.5 Control Element Assembly (CEA) Alignment 3.1.6 Shutdown CEA Insertion Limits 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Length or Part Strength CEA Insertion Limits 3.1.9 Special Test Exception (STE) -- SHUTDOWN MARGIN (SDM) 3.1.10 STE -- MODES 1 and 2 3.1.11 STE -- Reactivity Coefficient Testing 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Linear Heat Rate (LHR) 3.2.2 Planar Radial Peaking Factors (Fxy) 3.2.3 Azimuthal Power Tilt (Tq) 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 3.2.5 Axial Shape Index (ASI) 1.2.3 UNITS 1.2.3 VERDE UNITS i AMENDMENT NO. 44.7,152 PALO VERDE i AMENDMENT NO. 44-7,152

Definitions 1.1 1.1 Definitions (continued)

ENGINEERED SAFETY The ESF RESPONSE TIME shall be that time interval FEATURE (ESF) RESPONSE from when the monitored parameter exceeds its ESF TIME actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping. or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

Kn-lis the K effective calculated by considering the actual CEA configuration and assuming that the fully or partially inserted full strength CEA of highest worth is fully withdrawn. I LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE
1. LEAKAGE, such as that from pump seals or valve packing (except reactor coolant pump (RCP) seal water injection or leakoff).

that is captured and conducted to collection systems or a sump or collecting tank:

2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE: or
3. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System.

(continued)

PALO VERDE UNITS 1.2.3 1.1-4 AMENDMENT NO.435,152

Definitions 1.1 1.1 Definitions (continued)

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 3876 MWt for Units 1 and 3. and 3990 MWt for Unit 2.

REACTOR PROTECTIVE The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until electrical power to the CEAs drive mechanism is interrupted. The response time may be measured by means of any series of sequential, overlapping. or total steps so that the entire response time is measured. In lieu of measurement. response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC.

SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming:

a. All full strength CEAs (shutdown and I regulating) are fully inserted except for the single CEA of highest reactivity worth, which is assumed to be fully withdrawn. With any full strength CEAs not capable of being fully I inserted, the withdrawn reactivity worth of these CEAs must be accounted for in the determination of SDM and
b. There is no change in part length or part strength CEA position.

(continued)

PALO VERDE UNITS 1 AND 3 AMENDMENT NO. 45,152 PALO VERDE UNIT 2 1.1-6 AMENDMENT NO. 449,152

CEA Alignment 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Element Assembly (CEA) Alignment LCO 3.1.5 All full strength CEAs shall be OPERABLE. and all full strength and part length or part strength CEAs shall be aligned to within 6.6 inches (indicated position) of all other CEAs in their respective groups.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more CEAs A.1 Reduce THERMAL POWER 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> trippable and in accordance with misa igned from its the limits in the group by > 6.6 inches COLR.

and

  • 9.9 inches.

AND OR A.2 Restore CEA 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> One CEA trippable and alignment.

misaligned from its group by > 9.9 inches.

(continued)

PALO VERDE UNITS 1,2.3 3.1.5-1 AMENDMENT NO. 11-7,152

CEA Alignment 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Only one CEA position B.1 Restore at least two 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> indicator channel position indicator OPERABLE for one CEA channels to OPERABLE per CEA Group. status.

OR B.2 Verify the CEA 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> Group(s) with the inoperable position AND indicators are fully withdrawn or fully Once per 12 inserted while hours maintaining the thereafter.

insertion limits of LCO 3.1.6. LCO 3.1.7 and LCO 3.1.8.

C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time of Condition A or B not met OR One or more full strength CEAs I untrippable.

D. Two or more CEAs D.1 Open the reactor trip Immediately trippable and breakers.

misaligned from their group by > 9.9 inches.

PALO VERDE UNITS 1.2.3 3.1.5-2 AMENDMENT NO. Ali7,152

CEA Alignment 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify the indicated position of each full 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> strength and part length or part strength CEA is within 6.6 inches of all other CEAs in its group.

SR 3.1.5.2 Verify that, for each CEA. its OPERABLE CEA 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> position indicator channels indicate within 5.2 inches of each other.

SR 3.1.5.3 Verify full strength CEA freedom of 92 days movement (trippability) by moving each individual full strength CEA that is not fully inserted in the core at least 5 inches.

SR 3.1.5.4 Perform a CHANNEL FUNCTIONAL TEST of each 18 months reed switch position transmitter channel.

SR 3.1.5.5 Verify each full strength CEA drop time Prior to I

< 4.0 seconds. reactor criticality, after each removal of the reactor head PALO VERDE UNITS 1,2,3 3.1.5-3 AMENDMENT NO. 44-,152

Part Length or Part Strength CEA Insertion Limits 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Part Length or Part Strength Control Element Assembly (CEA) Insertion I Limits LCO 3.1.8 The part length or part strength CEA groups shall be limited to the insertion limits specified in the COLR. I APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Part length or part A.1 Restore part length or 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> strength CEA groups part strength CEA inserted beyond the groups to within the transient insertion limit.

limit.

OR A.2 Reduce THERMAL POWER 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> to less than or equal to that fraction of RTP specified in the COLR.

B. Part length or part B.1 Restore part length or 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> strength CEA groups part strength CEA inserted between the groups to within the long term steady state long term steady state insertion limit and insertion limit.

the transient insertion limit for intervals 2 7 effective full power days (EFPD) per 30 EFPD or > 14 EFPD per 365 EFPD interval.

(continued)

PALO VERDE UNITS 1.2,3 3.1.8-1 AMENDMENT NO. 41;-,152

Part Length or Part Strength CEA Insertion Limits 3.1.8 I ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br /> associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Verify part length or part strength CEA 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> I group position.

PALO VERDE UNITS 1.2,3 3.1.8-2 AMENDMENT NO. 44,152

STE-SDM 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 Special Test Exception (STE) - SHUTDOWN MARGIN (SDM)

LCO 3.1.9 During performance of PHYSICS TESTS, the requirements of:

LCO 3.1.2. "SHUTDOWN MARGIN (SDM)-Reactor Trip Breakers Closed":

LCO 3.1.6. "Shutdown Control Element Assembly (CEA) Insertion Limits", and LCO 3.1.7 "Regulating Control Element Assembly (CEA) Insertion Limits" may be suspended for measurement of CEA worth, provided shutdown reactivity equivalent to at least the highest estimated CEA worth (of those CEAs actually withdrawn) is available for trip insertion or the reactor is subcritical by at least the reactivity equivalent of the highest CEA worth.

APPLICABILITY: MODES 2 and 3 during PHYSICS TESTS.

NOTE----------------------------

Operation in MODE 3 shall be limited to 6 consecutive hours.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any full strength CEA A.1 Initiate boration to 15 minutes I not fully inserted and restore required less than the required shutdown reactivity.

shutdown reactivity available for trip insertion.

OR All full strength CEAs I inserted and the reactor subcritical by less than the above required shutdown reactivity equivalent.

PALO VERDE UNITS 1.2,3 3.1.9-1 AMENDMENT NO. 47W,152

STE-SDM 3.1.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify that the position of each CEA not 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> fully inserted is within the acceptance criteria for available negative reactivity addition.

SR 3.1.9.2 Verify each full strength CEA not fully Within 7 days I inserted is capable of full insertion when prior to tripped from at least the 50% withdrawn reducing SDM position. requirements to less than the limits of LCO 3.1.2 SR 3.1.9.3 ------------------- NOTE-------------------

Only required to be performed in Mode 3.

Verify that with all full strength CEAs 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> I fully inserted, the reactor is subcritical within the acceptance criteria.

PALO VERDE UNITS 1.2.3 3.1.9-2 AMENDMENT NO. 4-1-,152

STE - MODES 1 and 2 3.1.10 3.1 REACTIVITY CONTROL SYSTEMS 3.1.10 Special Test Exceptions (STE) - MODES 1 and 2 LCO 3.1.10 During performance of PHYSICS TESTS, the requirements of:

LCO 3.1.4. "Moderator Temperature Coefficient (MTC)";

LCO 3.1.5. "Control Element Assembly (CEA) Alignment";

LCO 3.1.6. "Shutdown Control Element Assembly (CEA)

Insertion Limits":

LCO 3.1.7. "Regulating Control Element Assembly (CEA)

Insertion Limits";

LCO 3.1.8. "Part Length or Part Strength CEA Insertion I Limits":

LCO 3.2.2. "Planar Radial Peaking Factors (Fxy)":

LCO 3.2.3. "AZIMUTHAL POWER TILT (Tq)";

LCO 3.2.5. "AXIAL SHAPE INDEX (ASI)"; and LCO 3.3.3, "Control Element Assembly Calculators (CEACs)"

may be suspended. provided THERMAL POWER is restricted to the test power plateau, which shall not exceed 85% RTP.

APPLICABILITY: MODES 1 and 2 during PHYSICS TESTS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Test power plateau A.1 Reduce THERMAL POWER 15 minutes exceeded. to less than or equal to the test power plateau.

B. Required Action and B.1 Suspend PHYSICS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion TESTS.

Time not met.

PALO VERDE UNITS 1.2,3 3.1.10-1 AMENDMENT NO. 41-7,152

STE - Reactivity Coefficient Testing 3.1.11 3.1 REACTIVITY CONTROL SYSTEMS 3.1.11 Special Test Exceptions (STE) - Reactivity Coefficient Testing LCO 3.1.11 During performance of PHYSICS TESTS, the requirements of:

LCO 3.1.7. "Regulating Control Element Assembly (CEA)

Insertion Limits";

LCO 3.1.8. "Part Length or Part Strength Control Element Assembly (CEA) Insertion Limits:" and I LCO 3.4.1. "RCS Pressure, Temperature and Flow limits" (LCO 3.4.1.b. RCS Cold Leg Temperature only) may be suspended, provided LHR and DNBR do not exceed the limits in the COLR.

APPLICABILITY: MODE 1 with Thermal Power > 20% RTP during PHYSICS TESTS:

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LHR or DNBR outside A.1 Reduce THERMAL POWER 15 minutes the limits specified to restore LHR and in the COLR. DNBR to within limits.

B. Required Action and B.1 Suspend PHYSICS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion TESTS.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.11.1 Verify LHR and DNBR do not exceed limits by Continuously performing SR 3.2.1.1 and SR 3.2.4.1.

PALO VERDE UNITS 1,2,3 3.1 .11-1 AMENDMENT NO. 44;,152

CEACs (Before CPC Upgrade) 3.3.3 ACTIONS CONDITION R REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Verify all full 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> strength and part length or part strength control element assembly (CEA) groups are fully withdrawn and maintained fully withdrawn, except during Surveillance testing pursuant to SR 3.1.5.3 or for control, when CEA group #5 may be inserted to a maximum of 127.5 inches withdrawn.

AND B.3 Verify the "RSPT/CEAC 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> Inoperable" addressable constant in each core

.protection calculator (CPC) is set to indicate that both CEACs are inoperable.

AND B.4 Verify the Control 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> Element Drive Mechanism Control System is placed in "STANDBY MODE" and maintained in "STANDBY MODE."

except during CEA motion permitted by Required Action B.2.

AND B.5 Perform SR 3.1.5.1. Once per 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> AND (continued)

________________________________ I I.

PALO VERDE UNITS 1,2,3 3.3.3-2 AMENDMENT NO. 64-,152

CEACs (After CPC Upgrade) 3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.1 Verify the departure from nucleate boiling 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> ratio requirement of LCO 3.2.4. "Departure from Nucleate Boiling Ratio (DNBR)." is met.

AND B.2.2 Verify all full strength and part length or part strength control element assembly (CEA) groups are fully withdrawn and maintained fully withdrawn, except during Surveillance testing pursuant to SR 3.1.5.3 or for control, when CEA group #5 may be inserted to a maximum of 127.5 inches withdrawn.

AND B.2.3 Verify the "RSPT/CEAC 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> Inoperable" addressable constant in each affected core protection calculator (CPC) is set to indicate that both CEACs are inoperable.

AND (continued)

PALO VERDE UNITS 1,2.3 3.3.3-6 AMENDMENT NO. 64-,152

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Palo Verde Nuclear Generating Station is located in Maricopa County.

Arizona. approximately 50 miles west of the Phoenix metropolitan area.

The site is comprised of approximately 4,050 acres. Site elevations range from 890 feet above mean sea level at the southern boundary to 1.030 feet above mean sea level at the northern boundary. The minimum distance from a containment building to the exclusion area boundary is 871 meters.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 241 fuel assemblies. Each assembly shall consist of a matrix of Zircaloy or ZIRLO fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations.

may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions. Other cladding material may be used with an approved exemption.

4.2.2 Control Element Assemblies The reactor core shall contain 76 full strength and either 13 part length or 13 part strength control element assemblies (CEAs).

The control section for the full strength CEAs shall be boron carbide with Inconel Alloy 625 cladding.

For units that have part length CEAs. the control section shall be Inconel Alloy 625 in the lower half, followed by perforated stainless steel tubing over the next 40%. and boron carbide pellets with Inconel Alloy 625 clad over the last 10% of the control section.

For units that have part strength CEAs. the control section shall be solid Inconel Alloy 625 slugs with Inconel Alloy 625 cladding.

(continued)

PALO VERDE UNITS 1.2.3 4.0-1 AMENDMENT NO. P--',152

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented inthe COLR for the following:
1. Shutdown Margin - Reactor Trip Breakers Open for Specification 3.1.1.
2. Shutdown Margin - Reactor Trip Breakers Closed for Specification 3.1.2.
3. Moderator Temperature Coefficient BOL and EOL limits for Specification 3.1.4.
4. Boron Dilution Alarm System for Specification 3.3.12.
5. CEA Alignment for Specification 3.1.5.
6. Regulating CEA Insertion Limits for Specification 3.1.7.
7. Part Length or Part Strength CEA Insertion Limits for Specification 3.1.8.
8. Linear Heat Rate for Specification 3.2.1.
9. Azimuthal Power Tilt - Tq for Specification 3.2.3.
10. DNBR for Specification 3.2.4.
11. Axial Shape Index for Specification 3.2.5.
12. Boron Concentration (Mode 6) for Specification 3.9.1.
b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described inthe following documents:

NOTE-------------------------

The COLR will contain the complete identification for each of the Technical Specification referenced topical reports used to prepare the COLR (i.e., report number, title, revision, date, and any supplements).

(continued)

PALO VERDE UNITS 1.2,3 5.6-3 AMENDMENT NO. 44;,152

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 Core Operating Limits Report (COLR) (continued)

1. "CE Method for Control Element Assembly Ejection Analysis," CENPD-0190-A. (Methodology for Specification 3.1.7. Regulating CEA Insertion Limits).
2. "The ROCS and DIT Computer Codes for Nuclear Design,"

CENPD-266-P-A. [Methodology for Specifications 3.1.1.

Shutdown Margin - Reactor Trip Breakers Open: 3.1.2.

Shutdown Margin - Reactor Trip Breakers Closed; 3.1.4, Moderator Temperature Coefficient BOL and EOL limits; 3.1.7, Regulating CEA Insertion Limits and 3.9.1. Boron Concentration (Mode 6)].

3. "Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80. Docket No. STN 50-470. "NUREG-0852 (November 1981). Supplements No. 1 (March 1983). No. 2 (September 1983). No. 3 (December 1987) [Methodology for Specifications 3.1.2. Shutdown Margin - Reactor Trip Breakers Closed: 3.1.4. Moderator Temperature Coefficient BOL and EOL limits: 3.3.12. Boron Dilution Alarm System: 3.1.5, CEA Alignment: 3.1.7. Regulating CEA Insertion Limits; 3.1.8. Part Length or Part Strength CEA Insertion Limits and 3.2.3. Azimuthal Power Tilt - TqO.
4. "Modified Statistical Combination of Uncertainties."

CEN-356(V)-P-A and "System 80. Inlet Flow Distribution."

Supplement 1-P to Enclosure 1-P to LD-82-054, (Methodology for Specification 3.2.4, DNBR and 3.2.5 Axial Shape Index).

5. "Calculative Methods for the CE Large Break LOCA Evaluation Model." CENPD-132. (Methodology for Specification 3.2.1. Linear Heat Rate).
6. "Calculative Methods for the CE Small Break LOCA Evaluation Model." CENPD-137-P. (Methodology for Specification 3.2.1, Linear Heat Rate).

(continued)

PALO VERDE UNITS 1.2.3 5.6-4 AMENDMENT NO. 44W,152

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 Core Operating Limits Report (COLR) (continued)

7. Letter: O.D. Parr (NRC) to F. M. Stern (CE), dated June 13, 1975 (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for:
5. .5.b.6.
8. Letter: K. Kniel (NRC) to A. E. Scherer (CE). dated September 27. 1977 (Evaluation of Topical Reports CENPD-133. Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.
9. "Fuel Rod Maximum Allowable Pressure." CEN-372-P-A.

(Methodology for Specification 3.2.1. Linear Heat Rate).

10. Letter: A. C. Thadani (NRC) to A. E. Scherer (CE).

dated April 10, 1990. ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

11. "Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3." [Methodology for Specifications 3.1.1. Shutdown Margin - Reactor Trip Breakers Open; 3.1.2. Shutdown Margin - Reactor Trip Breakers Closed: 3.1.4. Moderator Temperature Coefficient; 3.1.7, Regulating CEA Insertion Limits and 3.9.1. Boron Concentration (Mode 6)].
12. "Technical Manual for the CENTS Code." CE-NPD 282-P-A.

Volumes 1-3. [Methodology for Specifications 3.1.2.

Shutdown Margin-Reactor Trip Breakers Closed: 3.1.4.

Moderator Temperature Coefficient; 3.1.5. CEA Alignment; 3.1.7. Regulating CEA Insertion Limits; 3.1.8, Part Length or Part Strength CEA Insertion Limits and 3.2.3, Azimuthal Power Tilt- Tq).

13. CENPD-404-P-A. "Implementation of ZIRLOP Cladding Material in CE Nuclear Power Fuel Assembly Designs.
c. The core operating limits shall be determined such that all applicable limits (e.g.. fuel thermal mechanical limits, core thermal hydraulic limits. Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR. including any mid cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

PALO VERDE UNITS 1.2.3 5.6-5 AMENDMENT NO. F449,152

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