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| number = ML15105A039
| number = ML15105A039
| issue date = 04/10/2015
| issue date = 04/10/2015
| title = 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
| title = Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2014
| author name = Weber T N
| author name = Weber T
| author affiliation = Arizona Public Service Co
| author affiliation = Arizona Public Service Co
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter: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 CommissionWashington, DC 20555-0001
{{#Wiki_filter:10 CFR 50.46(a)(3)(ii)
Qaps Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road 102-07033-TNW/MDD/CJS                                                         Tonopah, AZ 85354 April 10, 2015 ATIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001


==Dear Sirs:==
==Dear Sirs:==


==Subject:==
==Subject:==
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3Docket Nos. STN 50-528/529/530Emergency Core Cooling System (ECCS) PerformanceEvaluation 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 performanceevaluation 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 PressurizedWater 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
Palo Verde Nuclear Generating Station (PVNGS)
* Wolf Creek 102-07033-TNW/MDD/CJSATTN: Document Control DeskU. S. Nuclear Regulatory CommissionEmergency 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/hscRegulatory 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 EvaluationModelsWestinghouse 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-15-015, dated March 26, 2015cc:M. L. DapasM. M. WatfordC. A. PeabodyNRC Region IV Regional AdministratorNRC NRR Project Manager for PVNGSNRC Senior Resident Inspector for PVNGS Summary of Cumulative Effects on Calculated Peak CladTemperature (PCT) for PVNGS Due to Changes/Errors inEmergency Core Cooling System (ECCS) PerformanceEvaluation 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 EvaluationModel 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 identifiedchanges 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 Summary 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 IdentifiedC. Absolute Sum of Cumulative 10 CFR 50.46Changes and Error CorrectionsD. 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 evaluationmodel, and the estimated cumulative effects of PCT impacts for changes and errorcorrections made since that AOR, remains less than 2200 OF.2 Westinghouse 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.comOur 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
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 2014 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 changes or errors that affected either the large break loss of coolant 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 LTC models that affect PCT.
The enclosures provide a more detailed discussion of the LOCA analyses in the Westinghouse (formerly Combustion Engineering) models for Pressurized Water Reactors (PWRs) ECCS performance analyses in calendar year 2014 for PVNGS.
No commitments are being made to the NRC by this letter.
Should you need further information regarding this submittal, please contact Michael D. Dilorenzo, Licensing Section Leader, at (623) 393-3495.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway - Diablo Canyon - Palo Verde
* Wolf Creek
 
102-07033-TNW/MDD/CJS 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 for Calendar Year 2014 Page 2 Sincerely,
(>vrv,.A,               w~ Oh           %I, Thomas N. Weber Department Leader, Regulatory Affairs TNW/MDD/CJS/hsc :       Summary of Cumulative Effects on Calculated Peak Clad Temperature (PCT) for PVNGS Due to Changes/Errors in Emergency Core Cooling System (ECCS) Performance Evaluation Models :        Westinghouse Electric Company Letter, Palo Verde Nuclear GeneratingStation Units 1, 2, and 3, 10 CFR 50.46 Annual Notification and Reporting for 2013, letter number LTR-TLA                     015, dated March 26, 2015 cc:
M. L. Dapas              NRC Region IV Regional Administrator M. M. Watford            NRC NRR Project Manager for PVNGS C. A. Peabody            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 Emergency Core Cooling System (ECCS) Performance Evaluation Models
 
Enclosure I Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models Table 1: Large Break LOCA Margin Summary Sheet for 2014 Plant Name:           Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name:          Arizona Public Service Company (APS)
Evaluation Model: Westinghouse (formerly Combustion Engineering) 1999 EM Peak Clad Temperature:       2106 OF (analysis of record reported in PVNGS UFSAR Section 6.3.3)
Net PCT        Absolute PCT Effect            Effect A. Cumulative 10 CFR 50.46 Changes and          APCT=    + 4 'F (Unit 3    + 4 OF (Unit 3 Error Corrections - Previously Reported (a)               Only)            Only)
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2014
: 1. None Identified for Units 1, 2 or 3      APCT =        + 0 IF            + 0 OF C. Absolute Sum of Cumulative 10 CFR 50.46      APCT =                    + 0 OF (Units 1 Changes and Error Corrections                                               and 2)
(Reflects evaluation of up to 8 Westinghouse NGF LUAs for Unit 3)                                       + 4 OF (Unit 3)
D. Licensing Basis PCT (Reported in UFSAR)                               2106 OF (Units 1
    + Cumulative PCT Assessments (Changes                                      and 2) and Error Corrections)                                                 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 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 2200 OF.
1
 
Enclosure 1 Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models Table 2: Small Break LOCA Margin Summary Sheet for 2014 Plant Name:           Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name:        Arizona Public Service Company (APS)
Evaluation Model:     Westinghouse (formerly Combustion Engineering) S2M Peak Clad Temperature:       1618OF (analysis of record reported in PVNGS UFSAR Section 6.3.3)
Net PCT      Absolute PCT Effect          Effect A. Cumulative 10 CFR 50.46 Changes and          APCT =      + 0 'F
* 0 OF Error Corrections - Previously Reported (a)
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2014
* 0 OF
: 1. None Identified                          APCT =      + 0 OF C. Absolute Sum of Cumulative 10 CFR 50.46      APCT =
* 0 OF Changes and Error Corrections D. Licensing Basis PCT (Reported in UFSAR) +                                 1618 OF Cumulative PCT Assessments (Changes and Error Corrections)
The 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 error corrections made since that AOR, remains less than 2200 OF.
2
 
Enclosure 2 Westinghouse Electric Company Letter, Palo Verde Nuclear GeneratingStation Units 1, 2, and 3, 10 CFR 50.46 Annual Notification and Reporting for 2014, letter number LTR-TLA-15-015, dated March 26, 2015
 
Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company Nuclear Services 20 International Drive Windsor, Connecticut 06095 USA Direct tel: (860) 731-6607 Direct fax: (860) 731-2480 e-mail: tatarcj@westinghouse.com Our ref:   LTR-TLA-15-015, Rev.0 March 26, 2015 Palo Verde Nuclear Generating Station Units 1, 2, and 3 10 CFR 50.46 Annual Notification and Reporting for 2014


==Dear Sir or Madam:==
==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'sQuality 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. TatarczukTransient & LOCA AnalysisVerifier: (Electronically Approved)*Douglas W AtkinsTransient & LOCA AnalysisApproved: (Electronically Approved)*Pat Kottas for John GhergurovichManager, 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 DescriptionNone N/A Westinghouse Non-Proprietary Class 3Attachment to LTR-TLA-1 5-015Rev. 0Page 1 of 7March 26, 2015
 
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 2014.
There were no changes, error corrections, or enhancements to the 1999 EM, which is the EM used in your plants' 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 2 evaluation 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, 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 (AOR) for your plants 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 AOR operation for 2014.
There are no PCT changes on the Unit 1 LBLOCA AOR, Unit 2 LBLOCA AOR, and Units 1, 2 and 3 SBLOCA AORs for 2014.
This letter is provided for your use in making a determination relative to the reporting requirements of 10 CFR 50.46. The information provided in this letter was prepared in accordance with Westinghouse's Quality Management System.
    *Electronicallyapprovedrecords are authenticatedin the electronic document management system.
                                    © 2015 Westinghouse Electric Company LLC All Rights Reserved
 
Westinghouse Non-Proprietary Class 3 LTR-TLA-15-015, Rev. 0 Page 2 of 2 March 26, 2015 Author:     (ElectronicallyApproved)*             Verifier:   (ElectronicallyApproved)*
Jessica L. Tatarczuk                              Douglas W Atkins Transient& LOCA Analysis                          Transient& LOCA Analysis Approved:   (ElectronicallyApproved)*
Pat Kottas for John Ghergurovich Manager,Transient & LOCA Analysis RACKUP SharePoint Check:
EMs applicable to Palo Verde Nuclear Generating Station Units 1, 2, and 3:
Appendix K Small Break - S2M Appendix K Large Break - 1999 EM 2014 Issues ITransmittal Letter     Issue Description None                    N/A
 
Westinghouse Non-Proprietary Class 3 Attachment to LTR-TLA-1 5-015 Rev. 0 Page 1 of 7 March 26, 2015


==Attachment:==
==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: 3/12/2015Analysis InformationEM: 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 ASSESSMENTSI None 0B. PLANNED PLANT MODIFICATION EVALUATIONS1 None 0C. 2014 ECCS MODEL ASSESSMENTSI 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.
LBLOCA and SBLOCA Rackup Sheets
 
Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large Break Plant Name:               Palo Verde Nuclear Generating Station Unit I Utility Name:             Arizona Public Service Revision Date:           3/12/2015 Analysis Information EM:             1999 EM                     Analysis Date:       8/31/2009             Limiting Break Size:         0.6 DEG/PD Fuel:           16x 16 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 1    None                                                                                       0 C. 2014 ECCS MODEL ASSESSMENTS I    None                                                                                       0 D. OTHER*
I 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.


==References:==
==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: 3/12/2015Analysis InformationEM: 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 ASSESSMENTSI. None 0B. PLANNED PLANT MODIFICATION EVALUATIONS1 None 0C. 2014 ECCS MODEL ASSESSMENTSI 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.
 
I. CVER-09-62, "Analyis of Record for Large Break LOCA ECCS Performance Analysis Including Replacement Steam Generators 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 Break Plant Name:               Palo Verde Nuclear Generating Station Unit I Utility Name:             Arizona Public Service Revision Date:           3/12/2015 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 ZIRLOTM cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp (OF)           Ref.     Notes LICENSING BASIS Analysis-Of-Record PCT                                                                                 1618 PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS I. None                                                                                       0 B. PLANNED PLANT MODIFICATION EVALUATIONS 1    None                                                                                       0 C. 2014 ECCS MODEL ASSESSMENTS I    None                                                                                       0 D. OTHER*
I . None                                                                                         0 LICENSING BASIS PCT + 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.


==References:==
==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: 3/12/2015Analysis InformationEM: 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 ASSESSMENTSI. None 0B. PLANNED PLANT MODIFICATION EVALUATIONSI None 0C. 2014 ECCS MODEL ASSESSMENTSI 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.
 
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 Break Plant Name:               Palo Verde Nuclear Generating Station Unit 2 Utility Name:             Arizona Public Service Revision Date:           3/12/2015 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 ZIRLOTM cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp (OF)           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    None                                                                                       0 C. 2014 ECCS MODEL ASSESSMENTS I    None                                                                                       0 D. OTHER*
I. 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.


==References:==
==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: 3/12/2015Analysis InformationEM: 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 ASSESSMENTSI .None 0B. PLANNED PLANT MODIFICATION EVALUATIONSI None 0C. 2014 ECCS MODEL ASSESSMENTSI 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.
 
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.
Notes:
None
 
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:           3/12/2015 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:         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.     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    None                                                                                       0 C. 2014 ECCS MODEL ASSESSMENTS I    None                                                                                       0 D. OTHER*
I . None                                                                                         0 LICENSING BASIS PCT + 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.


==References:==
==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: 3/12/2015Analysis InformationEM: 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 ASSESSMENTSI .Evaluation for the insertion of up to 8 NGF LUAs 4 2B. PLANNED PLANT MODIFICATION EVALUATIONSI None 0C. 2014 ECCS MODEL ASSESSMENTSI 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.
 
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 Break Plant Name:             Palo Verde Nuclear Generating Station Unit 3 Utility Name:           Arizona Public Service Revision Date:           3/12/2015 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:         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. Notes LICENSING BASIS Analysis-Of-Record PCT                                                                               2106         1 PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS I . Evaluation for the insertion of up to 8 NGF LUAs                                             4         2 B. PLANNED PLANT MODIFICATION EVALUATIONS I    None                                                                                       0 C. 2014 ECCS MODEL ASSESSMENTS I    None                                                                                       0 D. OTHER*
I. 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.


==References:==
==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: 3/12/2015Analysis InformationEM: 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 ASSESSMENTSI. None 0B. PLANNED PLANT MODIFICATION EVALUATIONSI None 0C. 2014 ECCS MODEL ASSESSMENTSI 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.
 
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
 
Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name:               Palo Verde Nuclear Generating Station Unit 3 Utility Name:             Arizona Public Service Revision Date:           3/12/2015 Analysis Information EM:             S2M                       Analysis Date:         3/22/2002             Limiting Break Size:         0.05 sq ft/PD Fuel:           16x 16 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 ZIRLOTM 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    None                                                                                       0 C. 2014 ECCS MODEL ASSESSMENTS I    None                                                                                       0 D. OTHER*
I . None                                                                                       0 LICENSING BASIS PCT + 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.


==References:==
==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}}
 
I . A-PV-FE-0149, Rev. 001, "Palo Verde Units 1,2, and 3 S2M Bounding SBLOCA ECCS Performance Analysis," March 2002.
Notes:
None}}

Latest revision as of 13:46, 5 February 2020

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  Arizona Public Service icon.png
Issue date: 04/10/2015
From: Weber T
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)

Qaps Palo Verde Nuclear Generating Station 5801 S. Wintersburg Road 102-07033-TNW/MDD/CJS Tonopah, AZ 85354 April 10, 2015 ATIN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

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 2014 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 changes or errors that affected either the large break loss of coolant 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 LTC models that affect PCT.

The enclosures provide a more detailed discussion of the LOCA analyses in the Westinghouse (formerly Combustion Engineering) models for Pressurized Water Reactors (PWRs) ECCS performance analyses in calendar year 2014 for PVNGS.

No commitments are being made to the NRC by this letter.

Should you need further information regarding this submittal, please contact Michael D. Dilorenzo, Licensing Section Leader, at (623) 393-3495.

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway - Diablo Canyon - Palo Verde

  • Wolf Creek

102-07033-TNW/MDD/CJS 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 for Calendar Year 2014 Page 2 Sincerely,

(>vrv,.A, w~ Oh %I, Thomas N. Weber Department Leader, Regulatory Affairs TNW/MDD/CJS/hsc : Summary of Cumulative Effects on Calculated Peak Clad Temperature (PCT) for PVNGS Due to Changes/Errors in Emergency Core Cooling System (ECCS) Performance Evaluation Models : Westinghouse Electric Company Letter, Palo Verde Nuclear GeneratingStation Units 1, 2, and 3, 10 CFR 50.46 Annual Notification and Reporting for 2013, letter number LTR-TLA 015, dated March 26, 2015 cc:

M. L. Dapas NRC Region IV Regional Administrator M. M. Watford NRC NRR Project Manager for PVNGS C. A. Peabody 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 Emergency Core Cooling System (ECCS) Performance Evaluation Models

Enclosure I Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models Table 1: Large Break LOCA Margin Summary Sheet for 2014 Plant Name: Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name: Arizona Public Service Company (APS)

Evaluation Model: Westinghouse (formerly Combustion Engineering) 1999 EM Peak Clad Temperature: 2106 OF (analysis of record reported in PVNGS UFSAR Section 6.3.3)

Net PCT Absolute PCT Effect Effect A. Cumulative 10 CFR 50.46 Changes and APCT= + 4 'F (Unit 3 + 4 OF (Unit 3 Error Corrections - Previously Reported (a) Only) Only)

B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2014

1. None Identified for Units 1, 2 or 3 APCT = + 0 IF + 0 OF C. Absolute Sum of Cumulative 10 CFR 50.46 APCT = + 0 OF (Units 1 Changes and Error Corrections and 2)

(Reflects evaluation of up to 8 Westinghouse NGF LUAs for Unit 3) + 4 OF (Unit 3)

D. Licensing Basis PCT (Reported in UFSAR) 2106 OF (Units 1

+ Cumulative PCT Assessments (Changes and 2) and Error Corrections) 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 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 2200 OF.

1

Enclosure 1 Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models Table 2: Small Break LOCA Margin Summary Sheet for 2014 Plant Name: Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name: Arizona Public Service Company (APS)

Evaluation Model: Westinghouse (formerly Combustion Engineering) S2M Peak Clad Temperature: 1618OF (analysis of record reported in PVNGS UFSAR Section 6.3.3)

Net PCT Absolute PCT Effect Effect A. Cumulative 10 CFR 50.46 Changes and APCT = + 0 'F

  • 0 OF Error Corrections - Previously Reported (a)

B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2014

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

The 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 error corrections made since that AOR, remains less than 2200 OF.

2

Enclosure 2 Westinghouse Electric Company Letter, Palo Verde Nuclear GeneratingStation Units 1, 2, and 3, 10 CFR 50.46 Annual Notification and Reporting for 2014, letter number LTR-TLA-15-015, dated March 26, 2015

Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company Nuclear Services 20 International Drive Windsor, Connecticut 06095 USA Direct tel: (860) 731-6607 Direct fax: (860) 731-2480 e-mail: tatarcj@westinghouse.com Our ref: LTR-TLA-15-015, Rev.0 March 26, 2015 Palo Verde Nuclear Generating Station Units 1, 2, and 3 10 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 Company emergency core cooling system (ECCS) performance evaluation models (EMs) and their application to your plants for calendar year 2014.

There were no changes, error corrections, or enhancements to the 1999 EM, which is the EM used in your plants' 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 2 evaluation 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, 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 (AOR) for your plants 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 AOR operation for 2014.

There are no PCT changes on the Unit 1 LBLOCA AOR, Unit 2 LBLOCA AOR, and Units 1, 2 and 3 SBLOCA AORs for 2014.

This letter is provided for your use in making a determination relative to the reporting requirements of 10 CFR 50.46. The information provided in this letter was prepared in accordance with Westinghouse's Quality Management System.

  • Electronicallyapprovedrecords are authenticatedin the electronic document management system.

© 2015 Westinghouse Electric Company LLC All Rights Reserved

Westinghouse Non-Proprietary Class 3 LTR-TLA-15-015, Rev. 0 Page 2 of 2 March 26, 2015 Author: (ElectronicallyApproved)* Verifier: (ElectronicallyApproved)*

Jessica L. Tatarczuk Douglas W Atkins Transient& LOCA Analysis Transient& LOCA Analysis Approved: (ElectronicallyApproved)*

Pat Kottas for John Ghergurovich Manager,Transient & LOCA Analysis RACKUP SharePoint Check:

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

Appendix K Small Break - S2M Appendix K Large Break - 1999 EM 2014 Issues ITransmittal Letter Issue Description None N/A

Westinghouse Non-Proprietary Class 3 Attachment to LTR-TLA-1 5-015 Rev. 0 Page 1 of 7 March 26, 2015

Attachment:

LBLOCA and SBLOCA Rackup Sheets

Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large Break Plant Name: Palo Verde Nuclear Generating Station Unit I Utility Name: Arizona Public Service Revision Date: 3/12/2015 Analysis Information EM: 1999 EM Analysis Date: 8/31/2009 Limiting Break Size: 0.6 DEG/PD Fuel: 16x 16 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 1 None 0 C. 2014 ECCS MODEL ASSESSMENTS I None 0 D. OTHER*

I 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.

References:

I. CVER-09-62, "Analyis of Record for Large Break LOCA ECCS Performance Analysis Including Replacement Steam Generators 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 Break Plant Name: Palo Verde Nuclear Generating Station Unit I Utility Name: Arizona Public Service Revision Date: 3/12/2015 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 ZIRLOTM cladding, value-added pellets, and erbia burnable absorbers.

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

A. PRIOR ECCS MODEL ASSESSMENTS I. None 0 B. PLANNED PLANT MODIFICATION EVALUATIONS 1 None 0 C. 2014 ECCS MODEL ASSESSMENTS I None 0 D. OTHER*

I . None 0 LICENSING BASIS PCT + 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.

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 Break Plant Name: Palo Verde Nuclear Generating Station Unit 2 Utility Name: Arizona Public Service Revision Date: 3/12/2015 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 ZIRLOTM cladding, value-added pellets, and erbia burnable absorbers.

Clad Temp (OF) 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 None 0 C. 2014 ECCS MODEL ASSESSMENTS I None 0 D. OTHER*

I. 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.

References:

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.

Notes:

None

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: 3/12/2015 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: 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. 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 None 0 C. 2014 ECCS MODEL ASSESSMENTS I None 0 D. OTHER*

I . None 0 LICENSING BASIS PCT + 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.

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 Break Plant Name: Palo Verde Nuclear Generating Station Unit 3 Utility Name: Arizona Public Service Revision Date: 3/12/2015 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: 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. Notes LICENSING BASIS Analysis-Of-Record PCT 2106 1 PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS I . Evaluation for the insertion of up to 8 NGF LUAs 4 2 B. PLANNED PLANT MODIFICATION EVALUATIONS I None 0 C. 2014 ECCS MODEL ASSESSMENTS I None 0 D. OTHER*

I. 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.

References:

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

Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name: Palo Verde Nuclear Generating Station Unit 3 Utility Name: Arizona Public Service Revision Date: 3/12/2015 Analysis Information EM: S2M Analysis Date: 3/22/2002 Limiting Break Size: 0.05 sq ft/PD Fuel: 16x 16 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 ZIRLOTM 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 None 0 C. 2014 ECCS MODEL ASSESSMENTS I None 0 D. OTHER*

I . None 0 LICENSING BASIS PCT + 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.

References:

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

Notes:

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