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Category:Annual Operating Report
MONTHYEARNL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 ML24086A5102024-03-25025 March 2024 Westinghouse Electric Company - 10 CFR 50.46 Annual Report for the AP1000 Plant Design NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 ML23090A1662023-03-28028 March 2023 Westinghouse, 10 CFR 50.46 Annual Report for the AP1000 Plant Design ML22083A1452022-03-18018 March 2022 Westinghouse Electric Co., 10 CFR 50.46 Annual Report for the AP1000 Plant Design NL-21-0606, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20202021-07-0101 July 2021 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2020 ML21090A0352021-03-24024 March 2021 Westinghouse Electric Company LLC, 10 CFR 50.46 Annual Report for the AP1000 Plant Design ND-20-1325, Report of CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report2020-12-11011 December 2020 Report of CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report NL-20-0630, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20192020-06-19019 June 2020 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2019 NL-20-0548, Submittal of Annual Radiological Environmental Operating Reports for 20192020-05-13013 May 2020 Submittal of Annual Radiological Environmental Operating Reports for 2019 ML20085H0802020-03-23023 March 2020 Westinghouse - 10 CFR 50.46 Annual Report for the AP1000 Plant Design NL-19-0650, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20182019-06-0505 June 2019 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2018 ML19088A1282019-03-26026 March 2019 Westinghouse - 10 CFR 50.46 Annual Report for the AP1OOO Plant Design NL-18-0539, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20172018-05-14014 May 2018 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2017 ND-18-0393, Submittal of 10 CFR 50.46 Annual Report2018-04-0606 April 2018 Submittal of 10 CFR 50.46 Annual Report ML18086A0252018-03-23023 March 2018 Westinghouse Electric Co., Submittal of 10 CFR 50.46 Annual Report for the AP1000 Plant Design ND-17-2038, Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report2017-12-11011 December 2017 Report of 10 CFR 50.59 Changes, Tests and Experiments and 10 CFR 52 Appendix D Departure Report NL-17-1560, CFR 72.48(d)(2)Biennial Report2017-09-19019 September 2017 CFR 72.48(d)(2)Biennial Report NL-17-0463, Transmittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20162017-04-20020 April 2017 Transmittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2016 NL-16-2660, Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20152016-12-21021 December 2016 Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2015 NL-15-0802, J.M. Farley, E.I. Hatch, Vogtle - Annual Non-Radioactive Environmental Operating Reports for 20142015-04-30030 April 2015 J.M. Farley, E.I. Hatch, Vogtle - Annual Non-Radioactive Environmental Operating Reports for 2014 NL-13-2576, CFR50.46 ECCS Evaluation Model Annual Report for 20122013-12-23023 December 2013 CFR50.46 ECCS Evaluation Model Annual Report for 2012 NL-13-1006, Annual Radiological Environmental Operating Reports for 20122013-05-15015 May 2013 Annual Radiological Environmental Operating Reports for 2012 NL-13-0889, Annual Radioactive Effluent Release Report for 20122013-04-30030 April 2013 Annual Radioactive Effluent Release Report for 2012 NL-11-2402, CFR 50.46 ECCS Evaluation Model Annual Reports for 20102011-12-21021 December 2011 CFR 50.46 ECCS Evaluation Model Annual Reports for 2010 NL-11-0888, Annual Radiological Environmental Operating Reports for 20102011-05-12012 May 2011 Annual Radiological Environmental Operating Reports for 2010 NL-11-0865, Annual Non-Radiological Environmental Operating Reports for 20102011-04-30030 April 2011 Annual Non-Radiological Environmental Operating Reports for 2010 NL-10-0905, Enclosure 3 - Vogtle, Units 1 and 2, Annual Radiological Environmental Operating Report for 20092010-05-14014 May 2010 Enclosure 3 - Vogtle, Units 1 and 2, Annual Radiological Environmental Operating Report for 2009 NL-10-0839, Submittal of Annual Non-Radiological Environmental Operating Report for 20092010-04-28028 April 2010 Submittal of Annual Non-Radiological Environmental Operating Report for 2009 NL-09-1838, CFR 50.46 ECCS Evaluation Model Annual Reports for 20082009-12-17017 December 2009 CFR 50.46 ECCS Evaluation Model Annual Reports for 2008 NL-09-0775, Annual Radiological Environmental Operating Reports for 20082009-05-14014 May 2009 Annual Radiological Environmental Operating Reports for 2008 NL-08-1735, Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20072008-12-19019 December 2008 Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 ML0713600572007-05-14014 May 2007 Annual Radiological Environmental Operating Report for 2006 ML0712204712007-04-30030 April 2007 Enclosure 3, Vogtle, Units 1 & 2 - Annual Radioactive Effluent Release Report for 2006 NL-07-0778, Submittal of Annual Radioactive Effluent Release Reports for 20062007-04-30030 April 2007 Submittal of Annual Radioactive Effluent Release Reports for 2006 NL-06-2513, E. I. Hatch, J. M. Farley, Vogtle, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20052006-12-14014 December 2006 E. I. Hatch, J. M. Farley, Vogtle, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2005 NL-05-1050, and Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20042005-06-25025 June 2005 and Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2004 NL-05-0761, Annual Non-Radiological Environmental Operating Reports for 20042005-04-25025 April 2005 Annual Non-Radiological Environmental Operating Reports for 2004 NL-04-0663, Annual Radiological Environmental Operating Reports for 20032004-05-14014 May 2004 Annual Radiological Environmental Operating Reports for 2003 ML0414001422004-05-14014 May 2004 Annual Radiological Environmental Operating Report for 2003 NL-03-0894, Annual Non-Radiological Environmental Operating Reports for 20022003-04-28028 April 2003 Annual Non-Radiological Environmental Operating Reports for 2002 ML0214203342002-05-13013 May 2002 Part B - Vogtle Electric Generating Plant - 2001 Annual Report ML0214203622002-05-13013 May 2002 Part a - Vogtle Electric Generating Plant - 2001 Annual Report ML0212803442002-04-22022 April 2002 2001 Annual Environmental Operating Report 2024-07-19
[Table view] Category:Letter
MONTHYEARML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology NL-24-0324, (Vegp), Unit 3, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 (Vegp), Unit 3, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information NL-24-0298, (Vegp), Unit 2, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 (Vegp), Unit 2, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter NL-24-0307, (Vegp), Unit 4, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 (Vegp), Unit 4, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements CY-22-005, LTR-24-0130 Nader Mamish, Vice President, Global Nuclear Regulatory Affairs, Westinghouse Electric Company, Letter Request for a Partial Vote on SECY-22-0052 - Proposed Rule: Alignment of Licensing Processes and Lesson Learned from New Rea2024-05-29029 May 2024 LTR-24-0130 Nader Mamish, Vice President, Global Nuclear Regulatory Affairs, Westinghouse Electric Company, Letter Request for a Partial Vote on SECY-22-0052 - Proposed Rule: Alignment of Licensing Processes and Lesson Learned from New Reac NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) IR 05000424/20244032024-05-0101 May 2024 Cyber Security Inspection Report 05000424/2024403 and 05000425/2024403 Public ML24120A2832024-04-30030 April 2024 Project Manager Reassignment NL-24-0170, Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report2024-04-25025 April 2024 Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000424/20240012024-04-23023 April 2024 –Integrated Inspection Report 05000424/2024001 and 05000425/2024001 NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report ML24079A0062024-04-10010 April 2024 – Proposed Alternative to the Requirements of ASME Code of Operation and Maintenance of Nuclear Power Plants for Pressure Isolation Valve Testing Frequency ML24030A9092024-04-10010 April 2024 Issuance of Amendment Nos. 224 and 207, Regarding Revision to Technical Specification 3.4.14 (Reactor Coolant System) Pressure Isolation Valve Leakage Surveillance Requirement 3.4.14.1 ML24096A1322024-04-0505 April 2024 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing and Order (EPID L-2024-LLA-0043) - Letter 2024-09-09
[Table view] |
Text
Westinghouse Non-Proprieta1y Class 3 DCP_NRC_003344 Page *1 of9
@ Westinghouse Westinghouse Electric Company 1000 Westinghouse Drive Cranberry Township, Pennsylvania 16066 USA U.S. Nuclear Regulat01y Commission Direct tel: 412-374-5093 Document Control Desk Direct fax: 724-940-8505 11555 Rockville Pike e-mail: hamerzs@westinghouse.com Rockville, MD 20852 Your Ref: Docket No.52-006 Our Ref: DCP NRC 003344 March 24, 2021
Subject:
10 CFR 50.46 Annual Report for the APlO00 Plant Design Pursuant to 10 CFR 50.46, "Acceptance cliteria for emergency core cooling systems for light-water nuclear power reactors", Westinghouse Electric Company, LLC is submitting this repo1t to document emergency core cooling system (ECCS) evaluation model changes or enors for the 2020 Model Year (i.e., 01/01/2020- 12/31/2020) that affect the peak cladding temperature (PCT) calculations for the APl000 plant design.
As described below, two APIO00 analyses of record (AORs) are repo1ted:
APIO00 Design Ce1tification AOR:
On December 30th, 2011 , the U.S. Nuclear Regulat01y Commission cettified an amendment to the Design Ce1tification Rule for the APl00O plant. As such, APl000 Design Control Document (DCD) Revision 19 documents the AOR for the APl000 Design Ce1tification. The limiting transient for the APl00O Design Ce1tification is the Best Estimate Large Break Loss-of-Coolant Accident (LBLOCA). Westinghouse last provided an annual rep01ting letter to the NRC in March 2020 (DCP_NRC_ 003340) which presented an estimated PCT of 2010°F for the LBLOCA evaluation. There are no new ECCS model changes that impact PCT for the 2020 model year.
The estimated PCT for LBLOCA remams at 2010°F and does not exceed the 10 CFR 50.46 (b)(l) acceptance crite1ion of 2200°F.
The surnmaiy of the PCT margin allocations and their bases for the APl000 Design Ce1tification AOR are provided in the Attachment 1.
APl000 Vogtle Units 3 & 4 AOR:
In addition to the AOR for the APl000 Design Ce1tification, the NRC has approved the APl0O0 Core Reference Rep01t (WCAP-17524-P-A), a generic topical which includes an ECCS "reanalysis" in the context of 10 CFR 50.46. The AOR contained in the Core Reference Repo1t (CRR) has also been approved for inco1poration into the Vogt.le Units 3 & 4 licenses via NRC License Amendment 52. Westinghouse last provided an annual rep01ting letter to the NRC in March 2020 (DCP_NRC_ 003340) which presented an estimated PCT of 2046°F for the LBLOCA evaluation. There are no new ECCS model changes that impact the limiting LBLOCA PCT for AP1000 is a trademark or registered trademark of Westinghouse Electric Company LLC, its affiliates and/or its subsidiaries in the United States ofAmerica and may be registered in other countries throughout the world. All rights reserved.
Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners
© 2021 Westinghouse Electric Company LLC All Rights Reserved
Westinghouse Non-Proprietary Class 3 the 2020 model year. As such, the estimated PCT for LBLOCA is 2046°F and does not exceed the IO CFR 50.46 (b)( I) acceptance criterion of2200°F.
Additionally, changes as part of the Automatic Depressurization System (ADS) and Core Makeup Tank (CMT) design parameters changes included in LAR-19-009 constitute a "reanalysis" in the context of IO CFR 50.46 for the small break loss of coolant accident (SBLOCA) analysis and have been approved for incorporation into the Vogtle Units 3&4 licenses via NRC License Amendments 176 (Unit 3) and 175 (Unit 4). The estimated LBLOCA PCT continues to be the limiting estimated PCT following the SBLOCA reanalysis.
The summary of the PCT margin allocations and their bases for the AP1000 Vogtle Units 3 & 4 AOR are provided in the Attachment 2.
By copy of this letter, COL Holders and COL Applicants are hereby notified of any changes or errors in the APl000 standard plant design PCT calculations as required by 10 CFR 50.46(a)(3)(iii). This letter contains site-specific evaluations for Vogtle Units 3 & 4.
Questions or requests for additional infonnation related to content and preparation of this infonnation should be directed to Westinghouse. Please send copies of such questions or requests to the respective COL Holders and COL Applicants referencing the amended API 000 Design Certification Rule for the APl 000 nuclear power plant. A representative for each COL Holder and COL Applicant is included on the cc: list of this letter.
Very truly yours, Zachary S. Harper Manager, APIO00 Licensing
/Attachments I. IO CFR 50.46 Annual Report for the AP I 000 Design Certification AOR, 2020 Model Year
- 2. 10 CFR 50.46 Annual Report for the APl000 Vogtle Units 3 & 4 AOR, 2020 Model Year Cc:
M. Dudek - U.S. NRC A. Zaremba - Duke/Progress M. Corletti - Westinghouse A. Bradford -U.S. NRC S. Franzone - FPL A. Schoedel - Westinghouse W. Ward -U.S.NRC R. Orthen -FPL M. Yuan - Westinghouse A. Chamberlain -SNC L. Oriani - Westinghouse D. McDevitt - Westinghouse M. Humphrey -SNC 0. Weaver - Westinghouse M. Sheaffer - Westinghouse E. Grant -SNC A. Konig - Westinghouse M . Barca - Westinghouse Y. Arafeh -SNC K. Hosack - Westin_ghouse M. Patterson - Westin_ghouse
<<'.) 2021 Westinghouse Electric Company LLC All Rights Reserved
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 3 of9 Attachment 1 10 CFR 50.46 Annual Repo1t for the APl000 Design Ce1tification AOR, 2020 Model Year
© 2021 Westinghouse Electric Company LLC All Rights Resen,ed
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 4 of 9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: APlOOO Utility Name: Westinghouse Nuclear Power Plants EM: ASTRUM (2004)
AOR
Description:
Best Estimate Large Break Summary Sheet Status:DCD PCT {°F) Reference# Note#
ANALYSIS-OF-RECORD 1837 Delta PCT Reporting ASSESSMENTS* {°AF) Refe1*ence # Note# Year**
- 1. Evaluation of Pellet Thennal 2012 Conductivity Degradation and 139 2 Peaking Factor Bumdown
- 2. Revised Heat Transfer 2013 11 3 Multiplier Distributions
- 3. Elrnr in Burst Strain Application 23 4 2013 AOR + ASSESSME TS PCT= 2010.0 Of
- The licensee should determine the rep011ability of these assessments pmsuant to 10 CFR 50 .46.
- The "Rep011ing Year" refers to the a1111ual reporting year in which this assessment was included.
REFERENCES 1 APP-GW-GL-700, Revision 19, "APl000 Design Control Document," June 201 I.
2 LTR-LIS-12-288, "Information Regarding the Evaluation of Fuel Pellet The1mal Conductivity Degradation and Peaking Factor Bumdown Including Analysis Input Changes for APl000 Large Break LOCA Analysis," June 2012.
3 LTR-LIS-13-357 , "APIO00 Plant IO CFR 50.46 Rep011 for Revised Heat Transfer Multiplier Distributions," July 2013 .
4 LTR-LIS- 14-41 "APIO00 Plant IO CFR 50.46 Repo11 for the HOTSPOT Burst Strain Enor Coffection,"
Janua1y 2014.
NOTES:
(a) None
© 2021 Westinghouse Electric Company LLC All Rights Reserved
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 5 of9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: APlOOO Utility Name: Westinghouse Nuclear Power Plants EM: NOTRUMP-AP AOR
Description:
Appendix K Small Break Summary Sheet Status:DCD PCT (0 F) Reference# Note#
Al~YSIS-OF-RECORD 1370 1 (a)
Delta PCT Reporting ASSESSMENTS* {°AF) Reference# Note# Year**
- 1. Adiabatic Heat-up Calculation 264 2 (a) 2010 AOR + ASSESSME TTS PCT= 1634.0 °F
- The licensee should determine the rep011ability of these assessments pmsuant to 10 CFR 50.46.
- The Rep011ing Year" refers to the ammal rep011ing year in which this assessment was included.
REFERENCES 1 APP-GW-GL-700, Revision 19, "APIO00 Design Control Document," June 2011.
2 LTR-LIS-10-373, "10 CFR 50.46 Repo11 for the Evaluation of APl000 SBLOCA IO-inch Transient Adiabatic Heat-up Calculation," June 2010.
NOTES:
(a) This is an adiabatic heat-up calculated PCT.
© 2021 Westinghouse Electric Company LLC All Rights Reserved
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 6 of9 Attachment 2 10 CFR 50.46 Annual Repo1t for the API000 Vogtle Units 3 & 4 AOR, 2020 Model Year
© 2021 Westinghouse Electric Company LLC All Rights Resen,ed
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 7 of9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: Vogtle Unit 3 and Unit 4 Utility Name: Southern Nuclear Operating Company EM: ASTRUM (2004)
AOR
Description:
Best Estimate Large Break Summary Sheet Status:Cunent PCT (0 F) Reference# Note#
Al~YSIS-OF-RECORD 1936 1 (a)
Delta PCT Reporting ASSESSMENTS* {°AF) Reference# Note# Year**
I. Revised Heat Transfer 2013 11 2 Multiplier Distributions
- 2. Elrnr in Burst Strain Application 23 3 2013
- 3. Design Change Rebaseline 2018 54 4,5 (b)
Evaluation
- 4. Evaluation ofRCP Design 2019 22 6,7 (c)
Changes - LAR 189 AOR + ASSESSME 'TS PCT= 2046.0 Of
- The licensee should detennine the rep01tability of these assessments pursuant to 10 CFR 50.46.
- The "Repo1ting Year" refers to the annual repo1ting year in which this assessment was included.
REFERENCES 1 WCAP-17524-P-A, Revision 1, "APl000 Core Reference Report," May 20 15.
2 LTR-LIS-13-357, "APl000 Plant 10 CFR 50.46 Rep01t for Revised Heat Transfer Multiplier Distributions " July 2013 .
3 LTR-LIS-14-41 , "APIO0O Plant IO CFR 50.46 Repo1t for the HOTSPOT Burst Strain Enor Con-ection,"
Januaiy 2014.
4 LTR-LIS- 18-393, "Update to the Vogtle Units 3 & 4 LBLOCA and SBLOCA IO CFR 50.46 PCT Summary Sheets for LAR-79," November 20 18.
5 ND-17-2074 (ML18029A243 ), " Containment Pressure Analysis (LAR-17-043)," December 20 17.
Approved byNRC November 7, 2018 as Amendments 147 (VEGP Un.it 3) aiid 146 (VEGP Unit 4)
(MLl 8289A742).
6 LTR-LIS- 17-39, "APIO00 Plant Suggested 10 CFR 50.46 Repo1ting Text and Updated LBLOCA PCT Summary Sheet for Evaluation of Reactor Coolant Pump (RCP) Design Cha11ges," Janua1y 2017 .
7 ND-18-1147 (ML18243A459), "Reactor Coolant System (RCS) Flow Coastdown (LAR-18-025) ," August 2018. Approved byNRC Febmaiy 25, 2019 as Amendments 155 (VEGPUnit3) and 154 (VEGPUnit4)
© 2021 Westinghouse Electric Company LLC All Rights Reserved
DCP_ NRC_003344 Westinghouse Non-Proprietary Class 3 Page 8 of 9 (ML19038A450).
NOTES:
(a) Value contains 2°F bias for PCT sensitivity to PRHR isolation, per Reference 1 response to CRR-008, Table 2 and Table 15.6.5-8.
(b) The design change rebaseline evaluation used cmTent code versions and accounts for design changes up to May 5, 2014 and plant model e1rnr conections.
(c) The RCP design changes evaluation assesses the impact ofDCP 5338 (APP-GW-GEE-5338), which is tied to DCP 4880 (APP-GW-GEE-4880). The evaluated changes include updated homologous curves and small changes to the pump rated conditions and rotor ine1tia.
© 2021 Westinghouse Electric Company LLC All Rights Reserved
DCP_NRC_003344 Westinghouse Non-Proprietary Class 3 Page 9 of9 LOCA Peak Cladding Temperature (PCT) Summary Plant Name: Vogtle Unit 3 and Unit 4 Utility Name: Southern Nuclear Operating Company EM: NOTRUMP-AP AOR
Description:
Appendix K Small Break Summary Sheet Status: Cw.Tent PCT (0 F) Reference# Noh.*#
Al~YSIS-OF-RECORD 1099 AOR + ASSESSME TS PCT= 1099.0 °F REFERENCES 1 ND-19-1142 (ML19273A953), "Automatic Depressurization System (ADS) and Core Makeup Tank (CMT) Design Parameters (LAR-19-009)," September 20 19. Approved by NRC March 11 , 2020 as Amendments 176 (VEGP Unit 3) and 175 (VEGP Unit 4) (ML20049A721/ML20049A808).
NOTES:
(a) None
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