ML15105A039

Palo Verde, Units 1, 2, and 3 - Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2014

ML15105A039
Person / Time
Site:	Palo Verde
Issue date:	04/10/2015
From:	Weber T N Arizona Public Service Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15105A039 (15)

Text

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

QapsPalo VerdeNuclear Generating Station5801 S. Wintersburg Road102-07033-TNW/MDD/CJS

Tonopah, AZ 85354April 10, 2015ATIN: Document Control DeskU.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3Docket Nos. STN 50-528/529/530 Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii)

Annual Reportfor Calendar Year 2014Pursuant to 10 CFR 50.46(a)(3)(ii),

Arizona Public Service Company (APS) isproviding a summary of the cumulative effects on calculated peak cladtemperature (PCT) for PVNGS due to changes or errors in ECCS performance evaluation models.There were no changes or errors that affected either the large break loss ofcoolant accident (LOCA) or the small break LOCA peak clad temperature (PCT) calculations for PVNGS Units 1, 2 or 3 for calendar year (CY) 2014.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 LTCmodels that affect PCT.The enclosures provide a more detailed discussion of the LOCA analyses inthe Westinghouse (formerly Combustion Engineering) models for Pressurized Water Reactors (PWRs) ECCS performance analyses in calendar year 2014for PVNGS.No commitments are being made to the NRC by this letter.Should you need further information regarding this submittal, please contactMichael D. Dilorenzo, Licensing Section Leader, at (623) 393-3495.

A member of the STARS (Strategic Teaming and Resource Sharing)

AllianceCallaway

-Diablo Canyon -Palo Verde

• Wolf Creek 102-07033-TNW/MDD/CJS ATTN: Document Control DeskU. S. Nuclear Regulatory Commission Emergency Core Cooling System (ECCS) Performance Evaluation Models,10 CFR 50.46(a)(3)(ii)

Annual Report for Calendar Year 2014Page 2Sincerely,

(>vrv,.A, w~Oh % I,Thomas N. WeberDepartment Leader,TNW/MDD/CJS/hsc Regulatory AffairsEnclosure 1:Enclosure 2:Summary of Cumulative Effects on Calculated Peak CladTemperature (PCT) for PVNGS Due to Changes/Errors inEmergency Core Cooling System (ECCS) Performance Evaluation ModelsWestinghouse Electric Company Letter, Palo Verde NuclearGenerating Station Units 1, 2, and 3, 10 CFR 50.46 AnnualNotification and Reporting for 2013, letter number LTR-TLA 015, dated March 26, 2015cc:M. L. DapasM. M. WatfordC. A. PeabodyNRC Region IV Regional Administrator NRC NRR Project Manager for PVNGSNRC Senior Resident Inspector for PVNGS Enclosure 1Summary of Cumulative Effects on Calculated Peak CladTemperature (PCT) for PVNGS Due to Changes/Errors inEmergency Core Cooling System (ECCS) Performance Evaluation Models Enclosure ISummary of Cumulative Effects on Calculated PCT for PVNGSDue to Changes/Errors in ECCS Performance Evaluation ModelsTable 1: Large Break LOCA Margin Summary Sheet for 2014Plant Name:Utility Name:Palo Verde Nuclear Generating Station Units 1, 2, and 3Arizona Public Service Company (APS)Evaluation Model: Westinghouse (formerly Combustion Engineering) 1999 EMPeak Clad Temperature:

2106 OF (analysis of record reported inSection 6.3.3)PVNGS UFSARNet PCTEffectAPCT= + 4 'F (Unit 3Only)A. Cumulative 10 CFR 50.46 Changes andError Corrections

-Previously Reported (a)B. 10 CFR 50.46 Changes and ErrorCorrections

-New for CY 20141. None Identified for Units 1, 2 or 3C. Absolute Sum of Cumulative 10 CFR 50.46Changes and Error Corrections (Reflects evaluation of up to 8Westinghouse NGF LUAs for Unit 3)D. Licensing Basis PCT (Reported in UFSAR)+ Cumulative PCT Assessments (Changesand Error Corrections)

APCT =APCT =+ 0 IFAbsolute PCTEffect+ 4 OF (Unit 3Only)+ 0 OF+ 0 OF (Units 1and 2)+ 4 OF (Unit 3)2106 OF (Units 1and 2)2110 OF (Unit 3)Notes: (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 10CFR 50.46(a)(3)(ii) and Submittal of Large Break Loss of Coolant AccidentReanalysis

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 hadpreviously 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 anacceptable evaluation model, and the estimated cumulative effects of PCT impactsfor changes and error corrections made since that AOR, remains less than 2200 OF.1 Enclosure 1Summary of Cumulative Effects on Calculated PCT for PVNGSDue to Changes/Errors in ECCS Performance Evaluation ModelsTable 2: Small Break LOCA Margin Summary Sheet for 2014Plant Name:Utility Name:Palo Verde Nuclear Generating Station Units 1, 2, and 3Arizona Public Service Company (APS)Evaluation Model: Westinghouse (formerly Combustion Engineering)

S2MPeak Clad Temperature:

1618OF (analysis of record reported in PVNGS UFSARSection 6.3.3)A. Cumulative 10 CFR 50.46 Changes andError Corrections

-Previously Reported (a)B. 10 CFR 50.46 Changes and ErrorCorrections

-New for CY 20141. None Identified C. Absolute Sum of Cumulative 10 CFR 50.46Changes and Error Corrections D. Licensing Basis PCT (Reported in UFSAR) +Cumulative PCT Assessments (Changesand Error Corrections)

APCT =APCT =APCT =Net PCTEffect+ 0 'F+ 0 OFAbsolute PCTEffect* 0 OF* 0 OF* 0 OF1618 OFThe sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of PCT impacts for changes and errorcorrections made since that AOR, remains less than 2200 OF.2 Enclosure 2Westinghouse Electric Company Letter, Palo Verde NuclearGenerating Station Units 1, 2, and 3, 10 CFR 50.46 AnnualNotification and Reporting for 2014, letter number LTR-TLA-15-015, dated March 26, 2015 Westinghouse Non-Proprietary Class 3Westinghouse Electric CompanyNuclear Services20 International DriveWindsor, Connecticut 06095USADirect tel: (860) 731-6607Direct fax: (860) 731-2480e-mail: tatarcj@westinghouse.com Our ref: LTR-TLA-15-015, Rev.0March 26, 2015Palo Verde Nuclear Generating Station Units 1, 2, and 310 CFR 50.46 Annual Notification and Reporting for 2014

Dear Sir or Madam:

This letter provides 10 CFR 50.46 reporting information pertaining to the Westinghouse Electric Companyemergency core cooling system (ECCS) performance evaluation models (EMs) and their application toyour plants for calendar year 2014.There were no changes, error corrections, or enhancements to the 1999 EM, which is the EM used in yourplants' large break loss of coolant accident (LBLOCA)

ECCS performance analysis in calendar year 2014.Additionally, there were no 2014 changes, error corrections, or enhancements to the Supplement 2evaluation model (S2M), which is the EM used in your plants' small break loss of coolant accident(SBLOCA)

ECCS performance analysis.

The peak cladding temperature (PCT) rackup sheets, along with your plants' specific evaluation text, areenclosed in the attachment.

The rackup sheets, which were obtained from the Westinghouse 10 CFR50.46 rackup database, identify the PCTs of the ECCS performance analyses of record (AOR) for yourplants and the PCT assessments associated with the AOR through the end of calendar year 2014.There were no changes to or errors found in the 1999 LBLOCA Evaluation Model in calendar year 2014.There were no changes to or errors found in the S2M SBLOCA Evaluation Model in calendar year 2014.There is a cumulative sum of the absolute magnitudes of PCT changes of 4 OF for the Unit 3 LBLOCA AORoperation for 2014.There are no PCT changes on the Unit 1 LBLOCA AOR, Unit 2 LBLOCA AOR, and Units 1, 2 and 3SBLOCA AORs for 2014.This letter is provided for your use in making a determination relative to the reporting requirements of 10CFR 50.46. The information provided in this letter was prepared in accordance with Westinghouse's Quality Management System.*Electronically approved records are authenticated in the electronic document management system.© 2015 Westinghouse Electric Company LLCAll Rights Reserved Westinghouse Non-Proprietary Class 3LTR-TLA-15-015, Rev. 0Page 2 of 2March 26, 2015Author: (Electronically Approved)*

Jessica L. Tatarczuk Transient

& LOCA AnalysisVerifier:

(Electronically Approved)*

Douglas W AtkinsTransient

& LOCA AnalysisApproved:

(Electronically Approved)*

Pat Kottas for John Ghergurovich

Manager, Transient

& LOCA AnalysisRACKUP SharePoint Check:EMs applicable to Palo Verde Nuclear Generating Station Units 1, 2, and 3:Appendix K Small Break -S2MAppendix K Large Break -1999 EM2014 IssuesITransmittal Letter Issue Description None N/A Westinghouse Non-Proprietary Class 3Attachment to LTR-TLA-1 5-015Rev. 0Page 1 of 7March 26, 2015

Attachment:

LBLOCA and SBLOCA Rackup Sheets Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large BreakPlant Name: Palo Verde Nuclear Generating Station Unit IUtility Name: Arizona Public ServiceRevision Date: 3/12/2015 Analysis Information EM: 1999 EM Analysis Date: 8/31/2009 Limiting Break Size: 0.6 DEG/PDFuel: 16x 16 System 80 SGTP (%): 10PLHGR (kW/ft):

13.1Notes: 1. Plant Configuration:

Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with ZIRLOTM cladding, value-added

pellets, and erbia burnable absorbers.

Clad Temp (IF) Ref. NotesLICENSING BASISAnalysis-Of-Record PCT 2106 1PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS I None 0B. PLANNED PLANT MODIFICATION EVALUATIONS 1 None 0C. 2014 ECCS MODEL ASSESSMENTS I None 0D. OTHER*I None 0LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 2106* It is recommended that the licensee determine if these PCT allocations should be considered with respect to10 CFR 50.46 reporting requirements.

References:

I. CVER-09-62, "Analyis of Record for Large Break LOCA ECCS Performance Analysis Including Replacement SteamGenerators and Simplified Head Implementation for PVNGS Units I, 2, and 3," August 2009.Notes:None Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small BreakPlant Name: Palo Verde Nuclear Generating Station Unit IUtility Name: Arizona Public ServiceRevision Date: 3/12/2015 Analysis Information EM: S2M Analysis Date: 3/22/2002 Limiting Break Size: 0.05 sq ft/PDFuel: 16x16 System 80 SGTP (%): 10PLHGR (kW/ft):

13.5Notes: 1. Plant Configuration:

Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with ZIRLOTM cladding, value-added

pellets, and erbia burnable absorbers.

Clad Temp (OF) Ref. NotesLICENSING BASISAnalysis-Of-Record PCT 1618PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS I. None 0B. PLANNED PLANT MODIFICATION EVALUATIONS 1 None 0C. 2014 ECCS MODEL ASSESSMENTS I None 0D. OTHER*I .None 0LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1618* It is recommended that the licensee determine if these PCT allocations should be considered with respect to10 CFR 50.46 reporting requirements.

References:

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

March 2002.Notes:None Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large BreakPlant Name: Palo Verde Nuclear Generating Station Unit 2Utility Name: Arizona Public ServiceRevision Date: 3/12/2015 Analysis Information EM: 1999 EM Analysis Date: 8/31/2009 Limiting Break Size: 0.6 DEG/PDFuel: 16x16 System 80 SGTP (%): 10PLHGR (kW/ft):

13.1Notes: 1. Plant Configuration:

Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with ZIRLOTM cladding, value-added

pellets, and erbia burnable absorbers.

Clad Temp (OF) Ref. NotesLICENSING BASISAnalysis-Of-Record PCT 2106 1PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS I. None 0B. PLANNED PLANT MODIFICATION EVALUATIONS I None 0C. 2014 ECCS MODEL ASSESSMENTS I None 0D. OTHER*I. None 0LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2106* It is recommended that the licensee determine if these PCT allocations should be considered with respect to10 CFR 50.46 reporting requirements.

References:

I .CVER-09-62, "Analysis of Record for Large Break LOCA ECCS Performance Analysis Including Replacement SteamGenerators and Simplified Head Implementation for PVNGS Units 1, 2, and 3," August 2009.Notes:None Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small BreakPlant Name: Palo Verde Nuclear Generating Station Unit 2Utility Name: Arizona Public ServiceRevision Date: 3/12/2015 Analysis Information EM: S2M Analysis Date: 3/22/2002 Limiting Break Size: 0.05 sq ft/PDFuel: 16x16 System 80 SGTP (%): 10PLHGR (kW/ft):

13.5Notes: I. Plant Configuration:

Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with ZIRLOTM cladding, value-added

pellets, and erbia burnable absorbers.

Clad Temp (OF) Ref. NotesLICENSING BASISAnalysis-Of-Record PCT 1618 1PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS I .None 0B. PLANNED PLANT MODIFICATION EVALUATIONS I None 0C. 2014 ECCS MODEL ASSESSMENTS I None 0D. OTHER*I .None 0LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1618* It is recommended that the licensee determine if these PCT allocations should be considered with respect to10 CFR 50.46 reporting requirements.

References:

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

March 2002.Notes:None Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large BreakPlant Name: Palo Verde Nuclear Generating Station Unit 3Utility Name: Arizona Public ServiceRevision Date: 3/12/2015 Analysis Information EM: 1999 EM Analysis Date: 8/31/2009 Limiting Break Size: 0.6 DEG/PDFuel: 16x16 System 80 SGTP (%): 10PLHGR (kW/ft):

13.1Notes: I. Plant Configuration:

Rated Core Power = 3990 MWt, Replacement Steam Generators.

2. Fuel Design: 16xI6 System 80 with ZIRLOTM cladding, value-added

pellets, and erbia burnable absorbers.

Clad Temp (IF) Ref. NotesLICENSING BASISAnalysis-Of-Record PCT 2106 1PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS I .Evaluation for the insertion of up to 8 NGF LUAs 4 2B. PLANNED PLANT MODIFICATION EVALUATIONS I None 0C. 2014 ECCS MODEL ASSESSMENTS I None 0D. OTHER*I. None 0LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2110* It is recommended that the licensee determine if these PCT allocations should be considered with respect to10 CFR 50.46 reporting requirements.

References:

I CVER-09-62.

"Analysis of Record for Large Break LOCA ECCS Performance Analysis Including Replacement SteamGenerators 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 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small BreakPlant Name: Palo Verde Nuclear Generating Station Unit 3Utility Name: Arizona Public ServiceRevision Date: 3/12/2015 Analysis Information EM: S2M Analysis Date: 3/22/2002 Limiting Break Size: 0.05 sq ft/PDFuel: 16x 16 System 80 SGTP (%): 10PLHGR (kW/ft):

13.5Notes: 1. Plant Configuration:

Rated Core Power = 3990 MWt. Replacement Steam Generators.

2. Fuel Design: 16x16 System 80 with ZIRLOTM cladding, value-added

pellets, and erbia burnable absorbers.

Clad Temp (IF) Ref. NotesLICENSING BASISAnalysis-Of-Record PCT 1618 1PCT ASSESSMENTS (Delta PCT)A. PRIOR ECCS MODEL ASSESSMENTS I. None 0B. PLANNED PLANT MODIFICATION EVALUATIONS I None 0C. 2014 ECCS MODEL ASSESSMENTS I None 0D. OTHER*I .None 0LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1618* It is recommended that the licensee determine if these PCT allocations should be considered with respect to10 CFR 50.46 reporting requirements.

References:

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

March 2002.Notes:None