ML13114A251
| ML13114A251 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 04/17/2013 |
| From: | Weber T Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06690-TNW/RKR | |
| Download: ML13114A251 (15) | |
Text
10 CFR 50.46(a)(3)(ii) ha ps Palo Verde Nuclear Generating Station 102-06690-TNW/RKR 5801 S. Wintersburg Road April 17, 2013 Tonopah, AZ 85354 ATTN: 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 2012 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 new errors or changes for calendar year (CY) 2012 that affected the PVNGS large break loss of coolant accident (LOCA) peak clad temperature (PCT) or the small break LOCA PCT calculations. Additionally, because PCT is not calculated as part of the post LOCA long-term cooling (LTC) analysis, there are no changes or errors in the LTC models that affect PCT.
The enclosures provide a more detailed discussion of the LOCA analysis in the Westinghouse (formerly Combustion Engineering) models for Pressurized Water Reactors (PWRs) ECCS performance analysis in calendar year 2012.
No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Mr. Robert K. Roehler, Licensing Section Leader, at (623) 393-5241.
Sincerely, Thomas N. Weber Department Leader, Regulatory Affairs TNW/RKR/hsc A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak - Diablo Canyon
- Palo Verde
- San Onofre
- South Texas
- Wolf Creek
102-06690-TNW/RKR April 17, 2013 NRC Document Control Desk ECCS Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii)
Annual Report For Calendar Year 2012 Page 2
Enclosures:
- 1. Summary of Cumulative Effects on Calculated Peak Clad Temperature (PCT) for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models
- 2. Westinghouse Electric Company Letter, Palo Verde Nuclear Generating Station Units 1, 2, and 3 10 CFR 50.46 Annual Notification and Reporting for 2012, letter number LTR-LAM-13-21, dated March 22, 2013 cc:
A. T. Howell III J. K. Rankin M. A. Brown NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC Senior Resident Inspector for PVNGS Summary of Cumulative Effects on Calculated Peak Clad Temperature (PCT) for PVNGS Due to Changes/Errors in ECCS Performance Evaluation Models Summary of Cumulative Effects on Calculated PCT Table 1: Large Break LOCA Margin Summary Sheet for 2012 Plant Name:
Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name:
Arizona Public Service Company Evaluation Model:
Westinghouse (formerly Combustion Engineering) 1999 EM Peak Clad Temperature:
2106OF (Analysis-of-Record reported in PVNGS UFSAR Section 6.3)
Net PCT Effect
+ 40F (Units 1 and 3 Only)
Absolute PCT Effect
+ 40 F (Units 1 and 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 2012
- 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 =
+ O°F
+ 0OF
+ 40 F (Unit 1)
" 00 F (Unit 2)
+ 40 F (Unit 3) 2110OF (Unit 1) 2106OF (Unit 2) 2110OF (Unit 3)
Note: (a) PVNGS reanalyzed the Large Break LOCA event with an NRC approved Evaluation Model in 2009, as reported in Letter No. 102-06113, 30-Day Report Pursuant to 10 CFR 50.46(a)(3)(ii) and Submittal of Large Break Loss of Coolant Accident Reanalysis Results, dated December 22, 2009 (NRC ADAMS Accession No. ML100040066). The reanalysis incorporated and corrected previously identified changes and errors, resetting the cumulative changes and error corrections that had previously been reported through the end of CY 2008 (NRC ADAMS Accession No. ML091810703).
The sum of the PCT from the most recent Analysis-of-Record (AOR) using an acceptable evaluation model, and the estimated cumulative effects of PCT impacts for changes and error corrections made since that AOR, remains less than 22000 F.
Page 1 Summary of Cumulative Effects on Calculated PCT Table 2: Small Break LOCA Margin Summary Sheet for 2012 Plant Name: Palo Verde Nuclear Generating Station Units 1, 2, and 3 Utility Name: Arizona Public Service Company Evaluation Model: Westinghouse (formerly Combustion Engineering) S2M Peak Clad Temperature: 1618°F (Analysis-of-Record reported in PVNGS UFSAR Section 6.3)
Net Absolute PCT PCT Effect Effect A.
Cumulative 10 CFR 50.46 Changes and Error APCT =
+ 0OF
+ 0OF Corrections - Previously Reported B.
10 CFR 50.46 Changes and Error Corrections
- New for CY 2012
- 1.
None Identified APCT =
+ 0°F
+ 0OF C.
Absolute Sum of Cumulative 10 CFR 50.46 APCT =
+ 0OF Changes and Error Corrections D.
Licensing Basis PCT (Reported in UFSAR) +
1618°F Cumulative PCT Assessments (Changes and Error Corrections)
The sum of the PCT from the most recent Analysis-of-Record (AOR) using an acceptable evaluation model, and the estimated cumulative effects of PCT impacts for changes and error corrections made since that AOR, remains less than 22000 F.
Page 2 Westinghouse Electric Company Letter, Palo Verde Nuclear Generating Station Units 1, 2, and 3 10 CFR 50.46 Annual Notification and Reporting for 2012, letter number LTR-LAM-13-21, dated March 22, 2013
Westinghouse Non-Proprietary Class 3 Westinghouse Electric Company efestinghouse Nuclear Services 20 International Drive Windsor, Connecticut 06095 USA Direct tel: (860) 731-6734 Direct fax: (860) 731-1196 e-mail: maguiraj@westinghouse.com Our ref:
LTR-LAM-13-21, Rev. 0 Page 1 of 9 March 22, 2013 Palo Verde Nuclear Generating Station Units 1, 2 and 3 10 CFR 50.46 Annual Notification and Reporting for 2012
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 2012.
There were no changes, error corrections or enhancements to the 1999 Evaluation Model (EM), which is the EM used in your plants' Large Break Loss-of-Coolant Accident (LBLOCA) ECCS performance analysis in calendar year 2012. In addition, there were no 2012 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 (AORs) for your plants and the PCT assessments associated with the AORs through the end of calendar year 2012.
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 (QMS).
On December 16, 2011, the Nuclear Regulatory Commission issued a request for information to Westinghouse regarding the evaluation of fuel thermal conductivity degradation (TCD) using Westinghouse codes and methods. Westinghouse provided a discussion of TCD impact on Large and Small Break LOCA for CE NSSS designs in Reference 1. It was concluded that conservatisms in the FATES models, and the application methodology of the FATES code, compensate for the effects of TCD. The conclusions presented in Reference 1 continue to apply.
© 2013 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 LTR-LAM-13-21, Rev. 0 Page 2 of 9 March 22, 2013
Reference:
- 1. Letter from J. A. Gresham (Westinghouse) to USNRC Document Control Desk, "Westinghouse Response to December 16, 2011 NRC Letter Regarding Nuclear Fuel Thermal Conductivity Degradation (TAC No. ME5186) (Proprietary)," LTR-NRC-12-18, February 17, 2012.
Author:
(Electronically Approved)*
A. J. Maguire LOCA Analysis & Methods Verifier:
(Electronically Approved)*
D. W. Atkins LOCA Analysis & Methods Approved:
(Electronically Approved)*
P. R. Kottas for J. Ghergurovich Manager, LOCA Analysis & Methods Attachment Electronically approved records are authenticated in the electronic document management system.
Attachment to LTR-LAM-1 3-21, Rev. 0 Page 1 of 7 March 22, 2013 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large Break Plant Name:
Utility Name:
Revision Date:
Palo Verde Nuclear Generating Station Unit 1 Arizona Public Service 2/28/2013 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 cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp (OF)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS I None B. PLANNED PLANT MODIFICATION EVALUATIONS I. Evaluation for the Insertion of 8 AREVA LTAs into Palo Verde C. 2012 ECCS MODEL ASSESSMENTS I None D. OTHER*
I None 2106 0
4 2
0 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 I, 2. and 3." August 2009.
2. LTR-OA-08-106, "10 CFR 50.46 Report for PVNGS Units 1. 2, and 3 for an Evaluation for the Insertion of 8 AREVA LTAs and the Correction of an Error in the Steam Generator Economizer Input," December 2008.
Notes:
None
Attachment to LTR-LAM-13-21, Rev. 0 Page 2 of 7 March 22, 2013 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name:
Utility Name:
Revision Date:
Palo Verde Nuclear Generating Station Unit 1 Arizona Public Service 2/28/2013 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: 16x] 6 System 80 with ZIRLO cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp ('F)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS I None B. PLANNED PLANT MODIFICATION EVALUATIONS I
Evaluation for the Insertion of 8 AREVA LTAs Into Palo Verde 2. Evaluation of the Simplified Head Assembly 1618 1
0 0
2 0
3 C. 2012 ECCS MODEL ASSESSMENTS I.None 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.
2. LTR-OA-08-106, " 10 CFR 50.46 Report for PVNGS Units 1, 2, and 3 for an Evaluation for the Insertion of 8 AREVA LTAs and the Correction of an Error in the Steam Generator Economizer Input," December 2008.
3. CVER-09-25, "Interim Evaluation of the Effects of SHA Implementation on PVNGS Units 1, 2, and 3 ECCS Performance,"
April 2009.
Notes:
None
Attachment to LTR-LAM-1 3-21, Rev. 0 March 22, 2013 Page 3 of 7 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:
2/28/2013 Analysis Information EM:
1999 EM Analysis Date:
8/31/2009 Limiting Break Size:
0.6 DEG/PD Fuel:
16x16 System 80 SGTP (%):
10 PLHGR (kW/ft):
13.1 Notes:
- 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.
- 2. Fuel Design: 16x16 System 80 with ZIRLO cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp (IF)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT 2106 1
A. PRIOR ECCS MODEL ASSESSMENTS I
None 0
B. PLANNED PLANT MODIFICATION EVALUATIONS I None 0
C. 2012 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
Attachment to LTR-LAM-1 3-21, Rev. 0 Page 4 of 7 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:
2/28/2013 Analysis Information EM:
S2M Analysis Date:
3/22/2002 Limiting Break Size:
Fuel:
16x 16 System 80 SGTP (%):
10 March 22, 2013 0.05 sq ft/PD PLHGR (kW/ft): 13.5 Notes:
- 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.
- 2. Fuel Design: 16xl 6 System 80 with ZIRLO cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp (°F)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT 1618 I
A. PRIOR ECCS MODEL ASSESSMENTS S.None 0
B. PLANNED PLANT MODIFICATION EVALUATIONS I. Evaluation of the Simplified Head Assembly 0
2 C. 2012 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.
2. CVER-09-25, "Interim Evaluation of the Effects of SHA Implementation on PVNGS Units 1. 2, and 3 ECCS Performance,"
April 2009.
Notes:
None
Attachment to LTR-LAM-1 3-21, Rev. 0 March 22, 2013 Page 5 of 7 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:
2/28/2013 Analysis Information EM:
1999 EM Analysis Date:
8/31/2009 Limiting Break Size:
0.6 DEG/PD Fuel:
16xl6 System 80 SGTP (%):
10 PLHGR (kW/ft):
13.1 Notes:
- 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.
- 2. Fuel Design: 16xl6 System 80 with ZIRLO' cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp (IF)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT 2106 1
A. PRIOR ECCS MODEL ASSESSMENTS I
None 0
B. PLANNED PLANT MODIFICATION EVALUATIONS I. Evaluation for the insertion of up to 8 NGF LUAs 4
2 C. 2012 ECCS MODEL ASSESSMENTS 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
Attachment to LTR-LAM-13-21, Rev. 0 March 22, 2013 Page 6 of 7 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:
2/28/2013 Analysis Information EM:
S2M Analysis Date:
3/22/2002 Limiting Break Size:
0.05 sq ft/PD Fuel:
16xl6 System 80 SGTP (%):
10 PLHGR (kW/ft):
13.5 Notes:
- 1. Plant Configuration: Rated Core Power = 3990 MWt, Replacement Steam Generators.
- 2. Fuel Design: 16x16 System 80 with ZIRLO cladding, value-added pellets, and erbia burnable absorbers.
Clad Temp (IF)
Ref.
Notes LICENSING BASIS Analysis-Of-Record PCT 1618 1
A. PRIOR ECCS MODEL ASSESSMENTS I
None 0
B. PLANNED PLANT MODIFICATION EVALUATIONS I Evaluation of the Simplified Head Assembly 0
2 2. Evaluation for the insertion of up to 8 NGF LUAs 0
3 C. 2012 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.
2 CVER-09-25, "Interim Evaluation of the Effects of SHA Implementation on PVNGS Units 1, 2, and 3 ECCS Performance,"
April 2009.
3 WCAP-17188-P, Rev. 2, "Palo Verde NGF LUA Engineering Report," March 2011.
Notes:
None
Attachment to LTR-LAM-1 3-21, Rev. 0 Page 7 of 7 March 22, 2013 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 2012 Issues Transmittal Letter Issue Description None