ML12121A173

Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2011

ML12121A173
Person / Time
Site:	Palo Verde
Issue date:	04/09/2012
From:	Weber T Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
102-06503-TNW/RAS/RKR
Download: ML12121A173 (14)

Text

10 CFR 50.46(a)(3)(ii)

ZA subsidiaryof Pinnacle West CapitalCorporation Thomas N. Weber Mail Station 7636 Palo Verde Nuclear Department Leader Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 102-06503-TNW/RAS/RKR April 9, 2012 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 50-528/529/530 Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report For Calendar Year 2011 Pursuant to 10 CFR 50.46(a)(3)(ii), Arizona Public Service Company (APS) is providing a summary of the cumulative effects on calculated peak clad temperature (PCT) for PVNGS due to changes or errors in ECCS performance evaluation models. There were no known errors or changes that affected the PVNGS large break loss of coolant accident (LOCA) peak clad temperature (PCT) or the small break LOCA PCT calculations. Additionally, because PCT is not calculated as part of the post LOCA long-term cooling (LTC) analysis, there are no changes or errors in the LTC models that affect PCT.

The enclosures provide a more detailed discussion of the LOCA analysis in the Westinghouse (formerly Combustion Engineering) models for Pressurized Water Reactors (PWRs) ECCS performance analysis in calendar year 2011.

No commitments are being 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.

Sincerely, TNW/RAS/RKR/hsc A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

• Comanche Peak -Diablo Canyon

• Palo Verde

• San Onofre ° South Texas

• Wolf Creek 14c

" IX

49-ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report Page 2

Enclosures:

1. Summary of Cumulative Effects on Calculated Peak Clad Temperature (PCT) for PVNGS Due to Changes/Errors in ECCS Performance Evaluation. Models

2. Westinghouse Electric Company Letter, "Palo Verde Nuclear Generating Station Units 1, 2, and 3 10 CFR 50.46 Annual Notification and Reporting for 2011," letter number LTR-LAM-1 2-5, dated March, 27, 2012 cc: E. E. Collins Jr. NRC Region IV Regional Administrator B. K. Singal NRC NRR Project Manager for PVNGS L. K. Gibson NRC NRR Project Manager J. R. Hall NRC NRR Senior Project Manager M. A. Brown NRC Senior Resident Inspector for PVNGS

ENCLOSURE 1 Summary of Cumulative Effects on Calculated Peak Clad Temperature (PCT) for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models

Table 1: Large Break LOCA Margin Summary Sheet for 2011 Plant Name: Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name: Arizona Public Service Company Evaluation Model: Westinghouse (formerly Combustion Engineering) 1999 EM Peak Clad Temperature: 2106'F (Analysis-of-Record reported in PVNGS UFSAR Section 6.3)

Net Absolute PCT PCT Effect Effect A. Cumulative 10 CFR 50.46 Changes and APCT + 4°F + 4°F Error Corrections - Previously (Units 1 and 3 (Units 1 and 3 Reported(a) Only) Only)

B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2011

1. None Identified APCT = + 0°F + 0°F C. Absolute Sum of Cumulative 10 CFR APCT = + 4 0 F (Unit 1) 50.46 Changes and Error Corrections + 0°F (Unit 2)

+ 4 0F (Unit 3)

D. Licensing Basis PCT (Reported in 21 10°F (Unit 1)

UFSAR) + Cumulative PCT 2106OF (Unit 2)

Assessments (Changes and Error 2110°F (Unit 3)

Corrections)

Note: (a) PVNGS reanalyzed the Large Break LOCA event with an NRC approved Evaluation Model in 2009, as reported in Letter No. 102-06113 "30-Day Report Pursuant to 10 CFR 50.46(a)(3)(ii) and Submittal of Large Break Loss of Coolant Accident Reanalysis Results," dated December 22, 2009 (NRC ADAMS Accession No. ML100040066). The reanalysis incorporated and corrected previously identified changes and errors, resetting the cumulative changes and error corrections that had previously been reported through the end of CY 2008 (NRC ADAMS Accession No. ML091810703).

The sum of the PCT from the most recent Analysis-of-Record (AOR) using an acceptable evaluation model, and the estimated cumulative effects of PCT impacts for changes and error corrections made since that AOR, remains less than 22000 F.

Table 2: Small Break LOCA Margin Summary Sheet for 2011 Plant Name: Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name: Arizona Public Service Company Evaluation Model: Westinghouse (formerly Combustion Engineering) S2M Peak Clad Temperature: 1618°F (Analysis-of-Record reported in PVNGS UFSAR Section 6.3)

Net Absolute PCT PCT Effect Effect A. Cumulative 10 CFR 50.46 Changes and APCT = + 0°F + 0°F Error Corrections - Previously Reported B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2011

1. None Identified APCT = + 0°F + 0°F C. Absolute Sum of Cumulative 10 CFR 50.46 APCT = + 0°F Changes and Error Corrections D. Licensing Basis PCT (Reported in UFSAR) 1618OF

+ Cumulative PCT Assessments (Changes and Error Corrections)

The sum of the PCT from the most recent Analysis-of-Record (AOR) using an acceptable evaluation model, and the estimated cumulative effects of PCT impacts for changes and error corrections made since that AOR, remains less than 22000 F.

ENCLOSURE 2 Westinghouse Electric Company Letter, "Palo Verde Nuclear Generating Station Units 1, 2, and 3 10 CFR 50.46 Annual Notification and Reporting for 2011 ,"

letter number LTR-LAM-12-5, dated March 27, 2012

1, Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company O Westinghouse Nudear-Services 20 International Drive Windsor, Connecticut 06095 USA Direct tel: (860) 731-6734 Direct faxc (860) 731-1196 e-mail: maguiraj@westinghouse.com Our ref: LTR-LAM-12-5, Rev. 0 Page 1 of 8 March 27, 2012 Palo Verde Nuclear Generating Station Unit 1, 2 and 3 10 CFR .50.46 Annual Notification and Reporting for,2011

Dear Sir or Madam:

This letter provides 10 CFR 50.46 reporting information pertaining to the Westinghouse Electric Company Emergency Core Cooling System (ECCS) performance Evaluation Models (EMs) and their application to your plants for calendar year 2011.

There were no changes, error corrections or enhancements to the 1999 Evaluation Model (EM), which is the EM used in your plant's Large Break Loss-of-Coolant Accident (LBLOCA) ECCS performance analysis in calendar year 2011. In addition, there were no 2011 changes, error corrections or enhancements to the Supplement 2 Evaluation Model (S2M), which is the EM used in your plant's Small Break Loss-of-Coolant Accident (SBLOCA) ECCS performance analysis.

The Peak Cladding Temperature (PCT) Rackup sheets along with your plant specific evaluation text are enclosed in the Attachment. The rackup sheets, which were obtained from the Westinghouse 10 CFR 50.46 Rackup database, identify the PCTs of the ECCS performance Analyses of Record (AORs) for your plants and the PCT assessments associated with the AORs through the end of calendar year 2011.

This letter is provided for your use in making a determination relative to the reporting requirements of 11 CFR 50.46. The information provided in this letter was prepared in accordance with Westinghouse's Quality. Management System (QMS).

Author: (Electronically Approved)* Verifier: (Electronically Approved)*

A. J. Maguire D. W. Atkins LOCA Analysis & Methods LOCA Analysis & Methods Verifier: (Electronically Approved)* Approved: (Electronically Approved)*

F. G. Small J. Ghergurovich LOCA Analysis & Methods Manager, LOCA Analysis & Methods Attachment ETlectronically approved recordsare authenticatedin the electronicdocument management system.

© 2012 Westinghouse Electric Company LLC All Rights Reserved

Attachment to LTR-LAM-12-5, Rev. 0 March 27, 2012 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large Break Plant Name: Palo Verde Nuclear Generating Station Unit 1 Utility Name: Arizona Public Service Revision Date: 1/5/2012 Analysis Information EM: 1999 EM Analysis Date: 8/31/2009 Limiting Break Size: 0.6 DEG/PD Fuel: 16x16 System 80 SGTP (%): 10 PLHGR (kW/ft): 13.1 Notes: 1.Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.

.2...Fuel-Design:16x 16 Sy.tem. 80 with 7IRLOT".cladding, value-added-pellets,and-erbia bumableabsorbers.

Clad Temp (IF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 2106 1 PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS I .None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS I . Evaluation for the Insertion of 8 AREVA LTAs into Palo Verde 4 2 C. 2011 ECCS MODEL ASSESSMENTS 1 .None 0 D. OTHER*

1 .None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2110

• It is recommended that the-licensee.determine if.these.PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.

Reference 1 . CVER-09-62, "Analyis of Record for Large-Break LOCA ECCS Performance Analysis Including-Replacement Steam Generators and Simplified Head Implementation for PVNGS Units 1, 2, and 3," August 2009.

2 . LTR-OA-08-106, "10 CFR 50.46 Report for PVNGS Units 1, 2, and 3 for an Evaluation for the Insertion of 8 AREVA LTAs and the Correction of an Error in the Steam Generator Economizer Input," December 2008.

Notes None

Attachment to LTR-LAM-A2-5, Rev. 0 March 27, 2012 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: Palo Verde Nuclear Generating Station Unit 1 Utility Name: Arizona Public Service Revision Date: 1/5/2012 Analysis Information EM: S2M Analysis Date: 3/22/2002 Limiting Break Size: 0.05 sq ft/PD Fuel: 16x16 System 80 SGTP(%): 10 PLHGR (kW/ft): 13.5 Notes: 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with Z1RLOTM cladding, value-added pellets, and erbia burnable absorbers.

Clad Temp (eF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1618 1 PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS 1 . None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS 1 . Evaluation for the Insertion of 8 AREVA LTAs Into Palo Verde 0 2 2 - Evaluation of the Simplified Head Assembly 0 3 C. 2011 ECCS MODEL ASSESSMENTS I . None 0 D.OTHER*

1 . None 0 LICENSING-BASIS PCTI + PCT ASSESSMENTS. PCT = 1618

• It is recommended that the licensee determine if these PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.

Reference I . A-PV-FE-0149, Rev. 001, "Palo Verde Units 1, 2 and 3 S2M Bounding SBLOCA ECCS Performance Analysis," March 2002.

2 . LTR-OA-08-106, "10 CFR 50.46 Report for PVNGS Units 1, 2, and 3 for an Evaluation for the Insertion of 8 AREVA LTAs and the Correction of an Error in the Steam Generator Economizer Input," December 2008.

3 . CVER-09-25, "Interim Evaluation of the Effects of SHA Implementation on PVNGS Units 1, 2, and 3 ECCS Performance," April 2009.

Notes None

Attachment to LTR-LAM-12-5, Rev. 0 March 27, 2012 Westinghouse LOCA Peak.Clad Temperature Summary for Appendix K Large Break Plant Name: Palo Verde Nuclear Generating Station Unit 2 Utility Name: Arizona Public Service Revision Date: 1/5/2012 Analysis Information EM: 1999 EM Analysis Date: 8/31/2009 Limiting Break Size: 0.6 DEG/PD Fuel: 16x16 System 80 SGTP (%): 10 PLHGR (kW/ft): 13.1 Notes: 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.

T 2.FuelDcsign:-16x16 System 80 with ZIRLO mcladding, value-added pellets, and erbia burnable absorbers.

Clad Temp (OF) Ref. N otes LICENSING BASIS Analysis-Of-Record PCT 2106 1 PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS 1 None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS 1 .None 0 C. 2011 ECCS MODEL ASSESSMENTS I .None 0 D. OTHER*

1 . None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2106

• It is recommended that the licensee determine if these PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.

Reference 1 - CVER-09-62, "Analysis of Record for Large Break LOCA ECCS Performance Analysis Including Replacement Steam Generators and Simplified Head Implementation for PVNGS Units 1, 2, and 3," August 2009.

Notes None

Attachment to LTR-LAM-12-5, Rev. 0 March 27, 2012 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: Palo Verde Nuclear Generating Station Unit 2 Utility Name: Arizona Public Service Revision Date: 1/5/2012 Analysis Information EM: S2M Analysis Date: 3/22/2002 Limiting Break Size: 0.05 sq ft/PD Fuel: 16x16 System 80 SGTP (%): 10 PLHGR (kW/ft): 13.5 Notes: 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.

T

2. Fuel Design: 16x16 System 80 with ZIRLJO M cladding, valueradded.pellets,.and erbia burnable absorbers.

Clad Temp (IF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1618 1 PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS I .None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS 1 . Evaluation of the Simplified Head Assembly 0 2 C. 2011 ECCS MODEL ASSESSMENTS I .None 0 D. OTHER*

1 .None 0 LICENSING BASIS PCT[ + PCI ASSESSMENTS PCT = 1618

• It is recommended that the licensee determine if these PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.

Reference 1 . A-PV-FE-0149, Rev. 001, "Palo Verde Units 1, 2 and 3 S2M Bounding SBLOCA ECCS Performance Analysis," March 2002.

2 . CVER-09-25, "Interim Evaluation of the Effects of SHA Implementation on PVNGS Units 1, 2, and 3 ECCS Performance," April 2009.

Notes None

Attachment to LTR-LAM-12-5, Rev. 0 March 27, 2012 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large Break Plant Name: Palo Verde Nuclear Generating Station Unit 3 Utility Name: Arizona Public Service Revision. Date;, 1/5/2012, Analysis Information EM: 1999 EM Analysis Date: 8/31/2009 Limiting Break Size: 0.6 DEG/PD Fuel: 16x16 System 80 SGTP (%): 10 PLHGR (kW/ft): 13.1 Notes: 1.Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with ZIRLO TM cladding, value-added pellets, and erbia burnable absorbers.

Clad Temp (IF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 2106 1 PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS I .None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS I . Evaluation for the insertion of up to 8 NGF LUAs 4 2 C. 2012 ECCS MODEL ASSESSMENTS 1 .None 0 D. OTHER*

1 .None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2110

• It is recommended that the licensee determine if these PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.

-Refcrcnces:

I CVER-09-62, "Analysis of Record for Large Break LOCA ECCS Performance Analysis Including Replacement Steam Generators and Simplified Head Implementation for PVNGS Units 1, 2, and 3," August 2009.

2 . WCAP-17188-P, Rev. 2, "Palo Verde NGF LUA Engineering Report," March 2011.

Notes:

None

Attachment to LTR-LAM-1 2-5, Rev. 0 March 27, 2012 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: Palo Verde Nuclear Generating Station Unit 3 Utility Name: ArizonaPublic Service Revision Date: 1/5/2012 Analysis Information EM: S2M Analysis Date: 3/22/2002 Limiting Break Size: 0.05 sq ftIPD Fuel: 16x16 System 80 SGTP (%): 10 PLHGR (kW/ft): 13.5 Notes: 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with ZIRLO Tm cladding, value-added pellets, and erbia burnable absorbers.

Clad Temp (IF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 1618 1 PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS I .None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS I Evaluation of the Simplified HeadAssembly 0 2 2 . Evaluation for the insertion of up to 8 NGF LUAs 0 3 C. 2012 ECCS MODEL ASSESSMENTS 1 .None 0 D. OTHER*

1 .None 0 LICENSING BASIS PCT + PCIT ASSESSMENTS PCT 1618

• It is recommended that the licensee determine if these PCT allocations should be considered with respect to 10 CFR 50.46 reporting requirements.

References:

1 A-PV-FE-0149, Rev. 001, "Palo Verde Units 1, 2, and 3 S2M Bounding SBLOCA ECCS Performance Analysis," March 2002.

2 . CVER-09-25, "Interim Evaluation of the Effects of SHA Implementation on PVNGS Units 1, 2, and 3 ECCS Performance,"

April 2009.

3 . WCAP-17188-P, Rev. 2, "Palo Verde NGF LUA Engineering Report," March 2011.

Notes:

None

Attachment to LTR-LAM-12-5, Rev. 0 March 27, 2012 RACKUP SharePoint Check:

EMs applicable to Palo Verde Nuclear Generating Station Unit 1, 2 and 3:

Appendix K Small Break - S2M Appendix K Large Break - 1999 EM 2011 Issues Transmittal Letter Issue Description None