ML15105A039
| 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
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, TNW/MDD/CJS/hsc Regulatory Affairs Enclosure 1: Enclosure 2: 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 Generating Station 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 M. M. Watford C. A. Peabody NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS 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: Utility Name: Palo Verde Nuclear Generating Station Units 1, 2, and 3 Arizona Public Service Company (APS)Evaluation Model: Westinghouse (formerly Combustion Engineering) 1999 EM Peak Clad Temperature:
2106 OF (analysis of record reported in Section 6.3.3)PVNGS UFSAR Net PCT Effect APCT= + 4 'F (Unit 3 Only)A. Cumulative 10 CFR 50.46 Changes and Error Corrections
-Previously Reported (a)B. 10 CFR 50.46 Changes and Error Corrections
-New for CY 2014 1. None Identified for Units 1, 2 or 3 C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections (Reflects evaluation of up to 8 Westinghouse NGF LUAs for Unit 3)D. Licensing Basis PCT (Reported in UFSAR)+ Cumulative PCT Assessments (Changes and Error Corrections)
APCT =APCT =+ 0 IF Absolute PCT Effect+ 4 OF (Unit 3 Only)+ 0 OF+ 0 OF (Units 1 and 2)+ 4 OF (Unit 3)2106 OF (Units 1 and 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 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: Utility Name: Palo Verde Nuclear Generating Station Units 1, 2, and 3 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)A. Cumulative 10 CFR 50.46 Changes and Error Corrections
-Previously Reported (a)B. 10 CFR 50.46 Changes and Error Corrections
-New for CY 2014 1. None Identified C. Absolute Sum of Cumulative 10 CFR 50.46 Changes and Error Corrections D. Licensing Basis PCT (Reported in UFSAR) +Cumulative PCT Assessments (Changes and Error Corrections)
APCT =APCT =APCT =Net PCT Effect+ 0 'F+ 0 OF Absolute PCT Effect* 0 OF* 0 OF* 0 OF 1618 OF 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 Generating Station 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.*Electronically approved records are authenticated in 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: (Electronically Approved)*
Jessica L. Tatarczuk Transient
& LOCA Analysis Verifier: (Electronically Approved)*
Douglas W Atkins Transient
& LOCA Analysis Approved: (Electronically Approved)*
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 T M 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: None