ML090760827

Supplemental Information for Request for Amendment to Technical Specification 5.6.5b, Core Operating Limits Report

ML090760827
Person / Time
Site:	Palo Verde
Issue date:	03/05/2009
From:	Hesser J Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-05967-JHH/DFS
Download: ML090760827 (10)

Text

10-CFR.50.90 LA MS A subsidiary of Pinnacle West Capital Corporation John H. Hesser Mail Station 7605 Palo Verde Nuclear Vice President Tel. 623-393-5553 P.O. Box 52034 Generating Station Nuclear Engineering Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-05967-JHH/DFS March 05, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-528, 50-529, and 50-530 Supplemental Information for Request for Amendment to Technical Specification 5.6.5b, Core Operating Limits Report (COLR)

Arizona Public Service Company (APS) in letter No. 102-05889, dated August 29, 2008, requested to amend Operating Licenses NPF-41, NPF-51, and NPF-74 for Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, respectively. Specifically, the proposed amendment would modify Technical Specification (TS) 5.6.5, Core Operating Limits Report (COLR), by updating TS 5.6.5b to reflect the current analytical methods used to determine the core operating limits in PVNGS Units 1, 2, and 3. The original submittal included a reference to the NRC Safety Evaluation for the Unit 2 Replacement of Steam Generators and Uprated Power Operation. In this supplement to the proposed TS amendment, APS is providing an additional reference to the NRC Safety Evaluation for the Units I and 3 Replacement of Steam Generators and Uprated Power Operation. The enclosure includes changes to Sections 2, 3 and 6 of the proposed amendment, and replacement marked up and retyped TS pages.

This change provides additional information that clarifies the August 29, 2008 submittal, does not expand the scope of that submittal as originally noticed, and does not change the U.S. Nuclear Regulatory Commission (NRC) staffs original proposed no significant hazards consideration determination as published in the Federal Register on November 4, 2008 (73 FR 65685).

There are no commitments made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.

A/&DI A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway 0 Comanche Peak 0 Diablo Canyon

• Palo Verde

• South Texas

• San Onofre 0 Wolf Creek

NRC Document Control Desk Supplemental Information for Request for Amendment to Technical Specification 5.6.5.b, Core Operating Limits Report (COLR)

Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on 3 i5 03 (Date)

Sincerely, DCM/TNW/DFS/

Enclosure:

Supplemental Information for Proposed Amendment to TS 5.6.5.b cc:

E. E. Collins Jr.

R. Hall R. I. Treadway A. V. Godwin T. Morales NRC Region IV Regional Administrator NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency (ARRA)

Arizona Radiation Regulatory Agency (ARRA)

Enclosure Supplemental Information for Proposed Amendment to TS 5.6.5 ENCLOSURE Supplemental Information for the Proposed Amendment to TS 5.6.5.b In Section 2 of the August 29, 2008 submittal, the following underlined change has been added:

d.

"Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003)"- and "Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."

[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; 3.1.5, CEA Alignment; 3.1.7, Regulating CEA Insertion Limits; 3.1.8, Part Length or Part Strength CEA Insertion Limits; 3.2.1, Linear Heat Rate; 3.2.3, Azimuthal Power Tilt; 3.2.4, DNBR; 3.2.5; Axial Shape Index; 3.3.12; Boron Dilution Alarm System (BDAS); and 3.9.1, Boron Concentration (Mode 6).]

In Section 3 of the August 29, 2008 submittal, the following underlined changes have been added:

d.

"Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation," (September 29, 2003) and "Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."

Various methodologies were provided in the PVNGS Unit 2 license amendment request on the replacement of steam generators and uprated power operations submitted on December 21, 2001, and as supplemented by letters to the NRC dated March 13, August 27, August 29, September 4, September 6, October 11, November 21, December 10, December 23, 2002, and March 11, June 10, July 25, and August 22, 2003. These various methodologies were approved with the issuance of that license amendment identified above.

These methodologies are used in the determination of shutdown margin with reactor trip breakers open, shutdown margin with reactor trip breakers closed, moderator temperature coefficient, CEA alignment, regulating CEA insertion limits, part length or part strength CEA insertion limits, linear heat rate, azimuthal power tilt, DNBR, axial shape index, boron dilution alarm setpoints, and boron 5

Enclosure Supplemental Information for Proposed Amendment to TS 5.6.5 concentration limits in Mode 6. (ADAMS Accession No. ML032720538). The Unit 2 listed methodologies were also approved for Units 1 and 3 in license Amendment Number 157, dated November 16, 2005. (ADAMS Accession No. ML0531130275)

In Section 6 of the August 29, 2008 submittal, the following underlined change has been added:

6.10 NRC letter dated November 16, 2005, "Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re: Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes" (ADAMS Accession No. ML053130275) 6

Enclosure Supplemental Information for Proposed Amendment to TS 5.6.5 ENCLOSURE, ATTACHMENT 1 Replacement Technical Specification Page Markups Pages:

5.6-5A 5.6-5B

Reporting Requirements 5.6 5.6 Reporting Requirements Rate; 3.2.3, Azimuthal Power Tilt; 3.2.4, DNBR; and J.2.b, Axial Shape Index.J

16.

CEN-191-P, "CETOP-D Code Structures and Modeling Metnods tor Calvert CliTtS I and 2.

NRC approval in Satety Evaluation Report related to Halo Verde Nuclear Generating Station, Unit 2 (PVNUS-Z)

Issuance of Amendment on Replacement ot )team Generators and Uprated.Power Uperation, (September 29, ZUUJ).

LMethodology for Specifications 3.1.1, Shutdown Margin

- Reactor rip breaKers Upen; 3.7.2, Shutdown Margin-Reactor rip BreaKers Closed; 3.1.4, Moderator lemperature Coefflcient; 3.2.1, Linear Heat Rate; 3.2.3, Azimuthal Power lilt; J.2.4, UNBR; and =.2.5, Axial Shape lndex.J

17.

"Safety Evaluation related to Palo Verde Nuclear Generating Station, unit 2 (PVNGS-2) issuance of Amendment on Replacement OT Steam Generators and Uprated Hower Uperation, (September 29, 2UU) and "Sfey Evaluation related to Palo0 Verde Nuclear g~nrating Station, Units 1 2 and3-Issuance of Amendments Re:

Re lacement of Steam Generators and Uorated Power DnionsandAssociated es November16, 205)

[Methodology for Specifications 3:1.1, Shutdown margin - Reactor irip breakers Upen:

1.1.Z, -Shutdofw-n Margin-Reactor irip BreaKers Closed; 3.1.4, Moderator lemperature Coeflfcient; 3.1.b,,EA Alignment; 3.1./, Regulating A insertion Limitsn T1.813 Hart Length or Hart Strength CLA insertion Limits; 3.Z.1, Linear Heat Rate; J.2.3, Azimuthal Power lilt; 3.2.4, UNBR; 3.2.b; Axial Shape Index; :.1.12; boron Uilution Alarm System MbAAS); and 1.9.1, boron Concentration (Mode b).j

18.

CEN-310-P-A, "CPC Methodology Changes for the CPC improvement Program."

Methodology Tor SpeciTications 3.2.1, Linear Heat Rate; J.Z.d, Azimuthal Hower lilt; 1.2.4, UNBK; and 3.2.b, Axial Snape Index.]

19.

CENPD-183-A, "Loss of Flow, C-E Methods for Loss of Flow Analysis.

LMethodology Tor Specifications -.2.1, Linear Heat Rate; J.2.3, Azimuthal Hower lilt; 3.2.4, UNBR; and

.2.5b, Axial Shape Index. j

20.

CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers.

LMetnodology for Specifications 1.1.I, Shutdown Margin - Reactor Trip breaKers Upen; 1.1.2, Shutdown Margin-Reactor rip breaKers Closed; and 1.1.4, Moderator lemperature CoefTicient.]

(continued)

PALO VERDE UNITS 1,2,3 5.6-5A AMENDMENT NO. 44-G, 152

Reporting Requirements 5.6 5.6 Reporting Requirements

21.

CEN-386-P-A, "Verification of the Acceptability of a 1-Pin burnup Limit OT bU MWU/KgU Tor UomDustlon Lngineering lb x ib HPW huei.

LMetnodology for SpeclT~cations 3.7.7, Shutdown Margin - Reactor Irip breakers Upen; 3.1.2, Shutdown Margin-Keactor Irip breaKers Ulosed; and 3.1.4, Moderator lemperature coeTTicient.

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 5.6-5B AMENDMENT NO. 473;, 161

Enclosure Supplemental Information for Proposed Amendment to TS 5.6.5 ENCLOSURE, ATTACHMENT 2 Replacement Retyped Technical Specification Pages Pages:

5.6-6 5.6-7

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

(continued)

Rate; 3.2.3, Azimuthal Power Tilt; 3.2.4, DNBR; and 3.2.5, Axial Shape Index.]

16.

CEN-191-P, "CETOP-D Code Structures and Modeling Methods for Calvert Cliffs 1 and 2."

NRC approval in "Safety Evaluation Report related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2)

Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003)."

[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; 3.2.1, Linear Heat Rate; 3.2.3, Azimuthal Power Tilt; 3.2.4, DNBR; and 3.2.5, Axial Shape Index.]

17.

"Safety Evaluation related to Palo Verde Nuclear Generating Station, Unit 2 (PVNGS-2)

Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) and "Safety Evaluation related to Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:

Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."

[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; 3.1.5, CEA Alignment; 3.1.7, Regulating CEA Insertion Limits; 3.1.8, Part Length or Part Strength CEA Insertion Limits; 3.2.1, Linear Heat Rate; 3.2.3, Azimuthal Power Tilt; 3.2.4, DNBR; and 3.2.5, Axial Shape Index; 3.3.12, Baron Dilution Alarm System (BDAS);

and 3.9.1, Boron Concentration (Mode 6).]

18.

CEN-310-P-A, "CPC Methodology Changes for the CPC Improvement Program."

[Methodology for Specifications 3.2.1, Linear Heat Rate; 3.2.3, Azimuthal Power Tilt; 3.2.4, DNBR; and 3.2.5, Axial Shape Index.]

19.

CENPD-183-A, "Loss of Flow, C-E Methods for Loss of Flow Analysis."

[Methodology for Specifications 3.2.1, Linear Heat Rate; 3.2.3, Azimuthal Power Tilt; 3.2.4, DNBR; and 3.2.5, Axial Shape Index.]

20.

CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers. '

[Methodology for Specifications 3.1.1, Shutdown Margin-Reactor Trip Breakers Open; 3.1.2, Shutdown Margin-Reactor Trip Breakers Closed; and 3.1.4, Moderator Temperature Coefficient.]

(continued)

PALO VERDE UNITS 1,2,3 5.6-6 AMENDMENT NO. 4-521,

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

(continued)

21.

CEN-386-P-A, "Verification of the Acceptability of a 1-Pin Burnup Limit of 60 MWD/kgU for Combustion Engineering

• 16 x 16 PWR Fuel."

[Methodology for Specifications 3.1.1, Shutdown Margin-Reactor Trip Breakers Open; 3.1.2,Shutdown Margin-Reactor Trip Breakers Closed; and 3.1.4, Moderator Temperature Coefficient.]

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 5.6-7 AMENDMENT NO. 4-64,