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Category:Annual Operating Report
MONTHYEARNL-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 ML0214203622002-05-13013 May 2002 Part a - Vogtle Electric Generating Plant - 2001 Annual Report ML0214203342002-05-13013 May 2002 Part B - Vogtle Electric Generating Plant - 2001 Annual Report ML0212803442002-04-22022 April 2002 2001 Annual Environmental Operating Report 2023-04-25
[Table view] Category:Letter
MONTHYEARML24032A0252024-02-0505 February 2024 NRC Initial Test Program and Operational Programs Integrated Inspection Report 05200026-2023009 ML24010A0712024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports and Recordkeeping and Suspicious Activity Reporting) ML24031A6102024-01-31031 January 2024 Cyber Security Inspection Report 05200026/2024401 - Public ML24029A0592024-01-30030 January 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report Enclosure 2, GAE-NRCD-RF-LR-000002 P-Attachment, Rev. 0 ML24016A1132024-01-30030 January 2024 Correction of Unit 1 Amendment Nos. 96 and 190 and Unit 2 Amendment Nos. 74 and 173 Adoption of Standard Technical Specifications Westinghouse Plants NL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 IR 05000424/20244032024-01-26026 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000424/2024403; 05000425/2024403 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23279A0042024-01-17017 January 2024 Amendment No. 194 to Remove Combined License Appendix C ML23347A2092024-01-17017 January 2024 Voluntary Requests for Data, Information, And/Or Observation ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23317A2072023-12-22022 December 2023 Issuance of Amendments 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-1448 ML23335A1222023-12-19019 December 2023 Safety Evaluation Regarding Implementation of Mitigating Strategies Related to Order EA-12-049 (EPID L-2023-LRQ-0002) - Letter ML23353A1702023-12-19019 December 2023 LAR-22-002, TS 3.8.3 Inverters Operating Completion Time Extension Letter ML23310A2922023-12-0707 December 2023 Issuance of Amendment for Exception to Regulatory Guide 1.163, LAR 23 007 ML23339A1812023-12-0707 December 2023 Correction Letter Regarding License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 ML23338A2182023-12-0606 December 2023 Project Manager Reassignment NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23289A1632023-11-28028 November 2023 Letter and Amendment 195 and 192 LAR-23-006R1 TS 3.1.9 More Restrictive Action NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 ML23312A3502023-11-14014 November 2023 Integrated Inspection Report 05200026/2023003 ML23318A4582023-11-14014 November 2023 Integrated Inspection Report 05200025/2023003 ML23306A3552023-11-0808 November 2023 NRC Initial Test Program and Operational Programs Integrated Inspection Report 052000/262023008 ML23268A0572023-11-0707 November 2023 Issuance of Amendments 194 & 191 Request for License Amendment Relocation of Technical Specification 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) IR 05000424/20234022023-11-0606 November 2023 Security Baseline Inspection Report 05000424/2023402 and 05000425/2023402 IR 05000424/20230032023-10-27027 October 2023 Integrated Inspection Report 05000424/2023003 and 05000425/2023003 ML23291A1512023-10-18018 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 0520026/2024401 ML23263A9852023-10-12012 October 2023 Issuance of Amendments Nos. 221 and 204, Regarding Technical Specification 5.5.11.C, Acceptance Criteria for Charcoal Filter Testing ML23283A0472023-10-0808 October 2023 Neop Letter Dated October 8, 2023 - Vogtle 3 & 4 - TS 3.7.6 License Amendment Request NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report ML23254A2032023-09-13013 September 2023 Initial Test Program and Operational Programs Inspection Report 05200025/2023013 ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report ML23234A2352023-09-0808 September 2023 Request for Withholding Information from Public Disclosure Notification of Full Compliance of Required Action for NRC Order EA-12-049 Mitigation Strategies for Beyond-Design-Basis External Events IR 05000424/20230912023-09-0505 September 2023 Plan Units 1 and 2 - NRC Investigation Report 2-2022-006 and Notice of Violation - NRC Inspection Report 05000424/2023091 and 05000425/2023091 ML23234A3002023-09-0101 September 2023 NRC Integrated Inspection Report 05200026/2023003 NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) ML23243A0092023-08-31031 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 & 4 (Report 05200025 2023005 & 05200026 2023005) ML23243B0252023-08-30030 August 2023 Exam Corporate Notification Letter (210 Day) IR 05000424/20230052023-08-29029 August 2023 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 & 2 - Report 05000424/2023005 and 05000425/2023005 NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) 2024-02-05
[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
© 2021 Westinghouse Electric Company LLC All Rights Reserved