ML24103A248
| ML24103A248 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/12/2024 |
| From: | Dilorenzo M Arizona Public Service Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 102-08795-MDD/CJS | |
| Download: ML24103A248 (11) | |
Text
A member of the STARS Alliance LLC Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek Palo Verde Nuclear Generating Station 5871 S. Wintersburg Road Tonopah, AZ 85354 102-08795-MDD/CJS April 12, 2024 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Renewed Operating License Nos. NPF-41, NPF-51 and NPF-74 Docket Nos. STN 50-528, 50-529, 50-530 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 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 cladding temperature (PCT) for the Palo Verde Nuclear Generating Station (PVNGS) due to changes or errors in emergency core cooling system (ECCS) performance evaluation models (EMs) for the calendar year (CY) 2023.
The following bullets summarize PVNGS ECCS performance relative to the 10 CFR 50.46 annual reporting requirements:
Large Break LOCA (LBLOCA) - During CY 2023 there were no new changes to, or errors discovered in, the Westinghouse 1999 EM, which is a 10 CFR 50.46(a)(1)(ii) and 10 CFR Part 50 Appendix K EM. There were, however, two minor errors evaluated in CY 2023 with respect to the Framatome EMF-2103 Revision 3 EM, which is a 10 CFR 50.46(a)(1)(i) realistic (that is, best estimate plus uncertainty) EM. Both errors had a delta PCT impact of 0 °F for PVNGS. The cumulative sum of the absolute magnitudes of delta PCT assessments, for all changes and errors identified since performance of the Westinghouse and Framatome LBLOCA analyses of record (AORs), was 0 °F throughout CY 2023 for all three PVNGS units. The sum of the LBLOCA AOR PCT and the delta PCT assessments throughout CY 2023 was 2130 °F for PVNGS Units 1 and 3 (Westinghouse CE16NGF and Westinghouse CE16STD fuel types), 2106 °F for PVNGS Unit 2 (Westinghouse CE16STD fuel type),
and 1752 °F for PVNGS Unit 2 (Framatome CE16HTP fuel type). These values are less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
Small Break LOCA (SBLOCA) - During CY 2023 there were no new changes to, or errors discovered in, the Westinghouse Supplement 2 (S2M) EM or the Framatome EMF-2328 Revision 0 and Supplement 1 Revision 0 EM. Both of these SBLOCA methodologies are 10 CFR 50.46(a)(1)(ii) and 10 CFR Part 50 Appendix K EMs. The cumulative sum of the absolute magnitudes of delta PCT assessments, for all changes and errors identified since performance of the Westinghouse and Framatome SBLOCA AORs, was 0 °F throughout CY 2023 for all three PVNGS units. The sum of the SBLOCA AOR PCT and the
102-08795-MDD/CJS ATTN: Document Control Desk U.S. Nuclear Regulatory Commission ECCS Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 Page 2 delta PCT assessments throughout CY 2023 was 1678 °F for PVNGS Units 1 and 3 (Westinghouse CE16NGF and Westinghouse CE16STD fuel types), 1618
°F for PVNGS Unit 2 (Westinghouse CE16STD fuel type), and 1620 °F for PVNGS Unit 2 (Framatome CE16HTP fuel type). These values are less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
PCT is not calculated as part of the post loss of coolant accident (LOCA) long-term cooling (LTC) analysis, therefore, there are no changes or errors in the LTC models that affect PCT.
The enclosure provides a more detailed discussion of the absolute PCT effects in the evaluation models for pressurized water reactors ECCS performance analyses in CY 2023 for PVNGS.
No commitments are being made to the NRC by this letter.
Should you need further information regarding this submittal, please contact me, at (623) 393-3495.
Sincerely, Michael D. DiLorenzo Department Leader Nuclear Regulatory Affairs - Licensing MDD/CJS/cr
Enclosure:
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 cc:
J. D. Monninger NRC Region IV Regional Administrator W. T. Orders NRC NRR Project Manager for PVNGS L. N. Merker NRC Senior Resident Inspector for PVNGS Dilorenzo, Michael D(Z99838)
Digitally signed by Dilorenzo, Michael D(Z99838)
Date: 2024.04.12 16:55:09 -07'00'
Enclosure 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 Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 1
Palo Verde Unit 1 Large Break Loss of Coolant Accident (LBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Westinghouse CE16NGF and CE16STD Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 1 Calendar Year (CY) 2023 Operating Cycle(s)
Cycles 24 and 25 Fuel Type(s)
Westinghouse CE16NGF and CE16STD Evaluation Model (EM):
Westinghouse 1999 EM EM
Description:
Appendix K Large Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 2130 °F 1, 2 1
Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 3
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
+ 0 °F
+ 0 °F C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 2130 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Westinghouse WCAP-18076-P, Revision 1, Reload Transition Safety Report for Palo Verde Nuclear Generating Station Units 1, 2, and 3 with Combustion Engineering 16x16 Next Generation Fuel, June 30, 2016.
- 2.
Westinghouse CN-TLA-14-016, Revision 2, Palo Verde Units 1, 2, and 3 LBLOCA Bounding ECCS Performance Analysis for NGF Transition, May 12, 2017.
- 3.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
Notes
- 1.
Palo Verde Unit 1 began CY 2023 in operating cycle 24, that units third fuel design transition cycle with 240 Westinghouse CE16NGF assemblies and 1 Westinghouse CE16STD center assembly in the reactor core. Unit 1 ended CY 2023 in operating cycle 25 with 241 Westinghouse CE16NGF assemblies in the reactor core. The PCT reported above (2130 °F) is bounding for both fuel types.
Enclosure Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 2
Palo Verde Unit 2 Large Break Loss of Coolant Accident (LBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Westinghouse CE16STD Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 2 Calendar Year (CY) 2023 Operating Cycle(s)
Cycles 24 and 25 Fuel Type(s)
Westinghouse CE16STD Evaluation Model (EM):
Westinghouse 1999 EM EM
Description:
Appendix K Large Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 2106 °F 1, 2 1
Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 3
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
+ 0 °F
+ 0 °F C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 2106 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Westinghouse 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 31, 2009.
- 2.
Westinghouse CN-LAM-09-33, Revision 0, LBLOCA ECCS Performance Analysis for Palo Verde Units 1, 2, and 3 for RSG and SHA Implementation, August 31, 2009.
- 3.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
Notes
- 1.
Palo Verde Unit 2 began CY 2023 in operating cycle 24, that units second fuel design transition cycle with 200 Framatome CE16HTP assemblies and 41 Westinghouse CE16STD assemblies in the reactor core. Unit 2 ended CY 2023 in operating cycle 25, that units third fuel design transition cycle with 241 Framatome CE16HTP assemblies in the reactor core. The PCT reported above (2106 °F) is bounding for Westinghouse CE16STD fuel only. The PCT for Framatome CE16HTP fuel is addressed on a separate summary sheet.
Enclosure Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 3
Palo Verde Unit 2 Large Break Loss of Coolant Accident (LBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Framatome CE16HTP Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 2 Calendar Year (CY) 2023 Operating Cycle(s)
Cycles 24 and 25 Fuel Type(s)
Framatome CE16HTP Evaluation Model (EM):
EMF-2103 Revision 3 EM
Description:
Realistic Large Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 1752 °F 1, 2, 3 1
Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 4
2 B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
- a.
Framatome CR 2022-1953, Downcomer to Upper Head Bypass Error
+ 0 °F
+ 0 °F 5
- b.
Framatome CR 2023-1134, Fuel Model Open Porosity Input Error
+ 0 °F
+ 0 °F 5
C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 1752 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Framatome 32-9268125, Revision 0, Palo Verde VQP Realistic Large Break LOCA (RLBLOCA) Uncertainty Analysis, February 21, 2018.
- 2.
Framatome ANP-3639P, Revision 1, Palo Verde Units 1, 2, and 3 Realistic Large Break LOCA Summary Report; Licensing Report, May 2018.
- 3.
Framatome ANP-3639P, Revision 1Q1P, Revision 0, Palo Verde Units 1, 2, and 3 Realistic Large Break LOCA Summary Report; NRC RAI Responses; Licensing Report, September 2019.
- 4.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
- 5.
Framatome Letter to APS, FS1-0071228-1.0, Framatome Annual Report Regarding Palo Verde LOCA Analysis Changes for 10 CFR 50.46 Reporting, January 25, 2024.
Notes
- 1.
Palo Verde Unit 2 began CY 2023 in operating cycle 24, that units second fuel design transition cycle with 200 Framatome CE16HTP assemblies and 41 Westinghouse CE16STD assemblies in the reactor core. Unit 2 ended CY 2023 in operating cycle 25, that units third fuel design transition cycle with 241 Framatome CE16HTP assemblies in the reactor core. The PCT reported above (1752 °F) is bounding for Framatome CE16HTP fuel only. The PCT for Westinghouse CE16STD fuel is addressed on a separate summary sheet.
- 2.
Changes and error corrections previously reported in Reference 4 include Framatome Condition Reports 2020-0441 (Radiation Enclosure Input Error), 2020-1165 (Radial Power Map Input Error), and 2020-1554 (Power History Input Error).
Enclosure Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 4
Palo Verde Unit 3 Large Break Loss of Coolant Accident (LBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Westinghouse CE16NGF and CE16STD Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 3 Calendar Year (CY) 2023 Operating Cycle(s)
Cycle 24 Fuel Type(s)
Westinghouse CE16NGF and CE16STD Evaluation Model (EM):
Westinghouse 1999 EM EM
Description:
Appendix K Large Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 2130 °F 1, 2 1
Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 3
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
+ 0 °F
+ 0 °F C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 2130 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Westinghouse WCAP-18076-P, Revision 1, Reload Transition Safety Report for Palo Verde Nuclear Generating Station Units 1, 2, and 3 with Combustion Engineering 16x16 Next Generation Fuel, June 30, 2016.
- 2.
Westinghouse CN-TLA-14-016, Revision 2, Palo Verde Units 1, 2, and 3 LBLOCA Bounding ECCS Performance Analysis for NGF Transition, May 12, 2017.
- 3.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
Notes
- 1.
Palo Verde Unit 3 began and ended CY 2023 in operating cycle 24, that units third fuel design transition cycle with 240 Westinghouse CE16NGF assemblies and 1 Westinghouse CE16STD center assembly in the reactor core. The PCT reported above (2130 °F) is bounding for both fuel types.
Enclosure Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 5
Palo Verde Unit 1 Small Break Loss of Coolant Accident (SBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Westinghouse CE16NGF and CE16STD Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 1 Calendar Year (CY) 2023 Operating Cycle(s)
Cycles 24 and 25 Fuel Type(s)
Westinghouse CE16NGF and CE16STD Evaluation Model (EM):
Westinghouse S2M EM
Description:
Appendix K Small Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 1678 °F 1, 2 1
Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 3
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
+ 0 °F
+ 0 °F C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 1678 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Westinghouse WCAP-18076-P, Revision 1, Reload Transition Safety Report for Palo Verde Nuclear Generating Station Units 1, 2, and 3 with Combustion Engineering 16x16 Next Generation Fuel, June 30, 2016.
- 2.
Westinghouse CN-TLA-14-020, Revision 1, Palo Verde Units 1, 2, and 3 SBLOCA Bounding ECCS Performance Analysis for NGF Transition, January 7, 2016.
- 3.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
Notes
- 1.
Palo Verde Unit 1 began CY 2023 in operating cycle 24, that units third fuel design transition cycle with 240 Westinghouse CE16NGF assemblies and 1 Westinghouse CE16STD center assembly in the reactor core. Unit 1 ended CY 2023 in operating cycle 25 with 241 Westinghouse CE16NGF assemblies in the reactor core. The PCT reported above (1678 °F) is bounding for both fuel types.
Enclosure Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 6
Palo Verde Unit 2 Small Break Loss of Coolant Accident (SBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Westinghouse CE16STD Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 2 Calendar Year (CY) 2023 Operating Cycle(s)
Cycles 24 and 25 Fuel Type(s)
Westinghouse CE16STD Evaluation Model (EM):
Westinghouse S2M EM
Description:
Appendix K Small Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 1618 °F 1
1 Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 2
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
+ 0 °F
+ 0 °F C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 1618 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Westinghouse A-PV-FE-0149, Revision 1, Palo Verde Units 1, 2 and 3 S2M Bounding SBLOCA ECCS Performance Analysis, March 22, 2002.
- 2.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
Notes
- 1.
Palo Verde Unit 2 began CY 2023 in operating cycle 24, that units second fuel design transition cycle with 200 Framatome CE16HTP assemblies and 41 Westinghouse CE16STD assemblies in the reactor core. Unit 2 ended CY 2023 in operating cycle 25, that units third fuel design transition cycle with 241 Framatome CE16HTP assemblies in the reactor core. The PCT reported above (1618 °F) is bounding for Westinghouse CE16STD fuel only. The PCT for Framatome CE16HTP fuel is addressed on a separate summary sheet.
Enclosure Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 7
Palo Verde Unit 2 Small Break Loss of Coolant Accident (SBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Framatome CE16HTP Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 2 Calendar Year (CY) 2023 Operating Cycle(s)
Cycles 24 and 25 Fuel Type(s)
Framatome CE16HTP Evaluation Model (EM):
EMF-2328 Revision 0 and Supplement 1 Revision 0 EM
Description:
Appendix K Small Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 1620 °F 1, 2, 3 1
Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 4
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
+ 0 °F
+ 0 °F C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 1620 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Framatome 32-9268122, Revision 0, Palo Verde VQP SBLOCA Transient Analyses, January 18, 2018.
- 2.
Framatome ANP-3640P, Revision 0, Palo Verde Units 1, 2, and 3 Small Break LOCA Summary Report; Licensing Report, March 2018.
- 3.
Framatome ANP-3640Q1P, Revision 0, Palo Verde Units 1, 2, and 3 Small Break LOCA Summary Report; NRC RAI Responses; Licensing Report, September 2019.
- 4.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
Notes
- 1.
Palo Verde Unit 2 began CY 2023 in operating cycle 24, that units second fuel design transition cycle with 200 Framatome CE16HTP assemblies and 41 Westinghouse CE16STD assemblies in the reactor core. Unit 2 ended CY 2023 in operating cycle 25, that units third fuel design transition cycle with 241 Framatome CE16HTP assemblies in the reactor core. The PCT reported above (1620 °F) is bounding for Framatome CE16HTP fuel only. The PCT for Westinghouse CE16STD fuel is addressed on a separate summary sheet.
Enclosure Summary of Cumulative Effects on Calculated PCT for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models 8
Palo Verde Unit 3 Small Break Loss of Coolant Accident (SBLOCA)
Peak Cladding Temperature (PCT) Summary Sheet Westinghouse CE16NGF and CE16STD Fuel Assemblies Utility Name:
Arizona Public Service Company (APS)
Plant Name:
Palo Verde Nuclear Generating Station, Unit 3 Calendar Year (CY) 2023 Operating Cycle(s)
Cycle 24 Fuel Type(s)
Westinghouse CE16NGF and CE16STD Evaluation Model (EM):
Westinghouse S2M EM
Description:
Appendix K Small Break PCT Reference(s)
Note(s)
Analysis of Record (AOR) 1678 °F 1, 2 1
Net PCT Effect Absolute PCT Effect Reference(s)
Note(s)
Assessments A. Cumulative 10 CFR 50.46 Changes and Error Corrections - Previously Reported
+ 0 °F
+ 0 °F 3
B. 10 CFR 50.46 Changes and Error Corrections - New for CY 2023
+ 0 °F
+ 0 °F C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections
+ 0 °F AOR + Assessments PCT = 1678 °F The sum of the PCT from the most recent AOR using an acceptable evaluation model, and the estimated cumulative effects of changes and error corrections made since that AOR, remains less than the 10 CFR 50.46(b)(1) regulatory limit of 2200 °F.
References
- 1.
Westinghouse WCAP-18076-P, Revision 1, Reload Transition Safety Report for Palo Verde Nuclear Generating Station Units 1, 2, and 3 with Combustion Engineering 16x16 Next Generation Fuel, June 30, 2016.
- 2.
Westinghouse CN-TLA-14-020, Revision 1, Palo Verde Units 1, 2, and 3 SBLOCA Bounding ECCS Performance Analysis for NGF Transition, January 7, 2016.
- 3.
APS Letter to NRC, 102-08601-MSC/CJS, Palo Verde Nuclear Generating Station Units 1, 2, and 3; Renewed Operating License Nos. NPF-41, NPF-51, and NPF-74; Docket Nos. STN 50-528, 50-529, 50-530; Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022, April 13, 2023. [NRC ADAMS Accession No. ML23103A431.]
Notes
- 1.
Palo Verde Unit 3 began and ended CY 2023 in operating cycle 24, that units third fuel design transition cycle with 240 Westinghouse CE16NGF assemblies and 1 Westinghouse CE16STD center assembly in the reactor core. The PCT reported above (1678 °F) is bounding for both fuel types.