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Category:Graphics incl Charts and Tables
MONTHYEARML23289A2302023-10-16016 October 2023 Discrimination Allegations Received Sept - 2023 ML23289A2292023-10-16016 October 2023 Allegations Substantiated with Regulatory Response - Sept 2023 ML23289A2272023-10-16016 October 2023 Allegations Substantiated - September 2023 ML23289A2232023-10-16016 October 2023 Allegations Received from All Sources External to the NRC - Sept 2023 ML23289A2212023-07-28028 July 2023 Allegations Open - Sept 2023 ML22348A0872023-07-25025 July 2023 Enclosure - VEGP Unit 4 - 103g - Final Memorandum Table ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23093A0862023-04-0303 April 2023 Dashboard Report 4-3-2023 ML22214B4932023-02-0808 February 2023 Enclosure 2 - Licensing Actions Status Table ML22214B4902023-02-0808 February 2023 Enclosure 1 - Operational Program Inspection Status Table ML23038A0082023-02-0707 February 2023 Construction Reactor Oversight Process Resources Report February 7, 2023 ML23033A0232023-02-0202 February 2023 Dashboard Report 2-2-2023 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22230C5162022-08-18018 August 2022 Dashboard Report 8-18-2022 ML22208A0242022-08-0101 August 2022 103g - Final Memorandum - Enclosure ML22206A1682022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22206A1712022-07-25025 July 2022 Dashboard Report 7-25-2022 ML22201A0442022-07-20020 July 2022 Voices Dashboard Report for Vogtle Unit 3 as of July 20, 2022 ML22186A0332022-07-0505 July 2022 Dashboard Report 7-5-2022 ML22186A0342022-07-0505 July 2022 Dashboard Report 7-5-2022 ML22173A0122022-06-22022 June 2022 Dashboard Report 6-22-2022 ML22144A0492022-05-24024 May 2022 Dashboard Report 5-24-2022 ML22144A0502022-05-24024 May 2022 Dashboard Report 5-24-2022 ND-22-0242, Request for Alternative: Alternative Requirements for Main Turbine System Valve Testing (VEGP 3&4-IST-ALT-02)2022-04-0808 April 2022 Request for Alternative: Alternative Requirements for Main Turbine System Valve Testing (VEGP 3&4-IST-ALT-02) ML22091A3162022-04-0101 April 2022 NRC Initial Test Program and Operational Programs Inspection Reports 05200025/2022002, 05200026/2022002 ML22087A0962022-03-28028 March 2022 Dashboard Report 3-28-2022 ML21277A0762021-10-0404 October 2021 Vog 4 Dashboard 10-4-2021 ML21215A0072021-08-0303 August 2021 Dashboard Report 8-2-2021 ML21215A0062021-08-0303 August 2021 Dashboard Report 8-2-2021 ML21160A0382021-06-0909 June 2021 Construction Reactor Oversight Process Resources Report June 2021 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21008A0042021-01-0404 January 2021 Dashboard Report 1-4-2021 ML20343A0742020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20281A3872020-10-0101 October 2020 Dashboard Report 10-1-2020 ML20281A4002020-10-0101 October 2020 Dashboard Report 10-1-2020 ML20183A0902020-09-24024 September 2020 Initial Commission Memo Regarding Status of ITAAC Closure, Inspection, and Licensing Activities for Vogtle Electric Generating Plant, Unit 3 ML20191A3982020-08-14014 August 2020 Table 2 - Vogtle, Units 3 and 4, Resident Inspector Inspection Samples and Hours ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ML20121A2902020-04-30030 April 2020 Construction Reactor Oversight Process Resources 1st Quarter CY2020 ML20038A3072020-02-0707 February 2020 Construction Reactor Oversight Process Resources. Quarterly Update. 1st Quarter 2020 ML20035C5542020-02-0404 February 2020 Attachment 1 - Targeted ITAAC Listing for Vogtle Electric Generating Plant Units 3 and 4 ML20035C5612020-02-0404 February 2020 Attachment 2 - Targeted ITAAC Family Listing for Vogtle Electric Generating Plant Units 3 and 4 ML20035C5702020-02-0404 February 2020 Attachment 3 - Targeted ITAAC Changes for Vogtle Electric Generating Plant Units 3 and 4 ML20007D9042020-01-0808 January 2020 Table of Proposed ROP Baseline Samples for Vogtle Site ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15106A3612015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Example Vogtle 1 and 2, Change Justification Matrix ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T ML14078A6202014-04-0101 April 2014 Enclosure 2 - SAMG Entry Flowcharts 2023-07-03
[Table view] Category:Report
MONTHYEARML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML24004A2192024-01-0808 January 2024 Construction Reactor Oversight Process Performance Metric Report for Calendar Year 2023 ND-23-0025, Compliance with Order EA-12-0492023-08-21021 August 2023 Compliance with Order EA-12-049 ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML22348A0882023-07-25025 July 2023 VEGP Unit 4 - 103g - Basis Document ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ML23156A1882023-06-0505 June 2023 Construction Reactor Oversight Process Resources Report June 5, 2023 ML23121A0392023-05-0101 May 2023 Dashboard Report 5-1-2023 ML23003A0412023-01-0303 January 2023 Construction Reactor Oversight Process Resources Report January 3, 2023 ND-22-0817, Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection2022-11-0404 November 2022 Enclosures 1 and 2: Proposed Alternative Inspection Requirements for Steam Generator Nozzle to Reactor Coolant Pump Casing Welds and Alternative for Use of Code Case 648-2 for Inservice Inspection ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML20290A2762022-08-0101 August 2022 10CFR52.103(g) Basis Document NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 ML22179A1462022-06-15015 June 2022 Tier 1, Revision 10, Updated Through 04/22/2022 ML22159A1712022-06-0808 June 2022 Construction Reactor Oversight Process Resources Report June 8, 2022 ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ML22089A0412022-03-30030 March 2022 Construction Reactor Oversight Process Resources Report March 30 2022 ND-22-0003, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2022-01-0606 January 2022 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21277A0762021-10-0404 October 2021 Vog 4 Dashboard 10-4-2021 ND-21-0848, Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised)2021-10-0101 October 2021 Enclosure - Unit 4 Operator Candidates Requesting Credit for Unit 3 Written Examination and Operating Test (Revised) IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML21179A0972021-06-15015 June 2021 to Tier 1 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 ND-21-0342, Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 42021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtie Unit 4 ML21090A2092021-03-31031 March 2021 Construction Reactor Oversight Process Resources Report March 2021 ML21040A1672021-02-0909 February 2021 (Vegp), Units 3 and 4, Revision to Westinghouse Non-Proprietary Technical Description of the Flaw Tolerance Evaluation Conducted on the Subject Weldolet Branch Connections ML20358A1822020-12-31031 December 2020 LTR-SDA-20-096-NP, Revision 1, Flaw Tolerance Evaluation to Assess Lack of Inspection Coverage of AP1000 14 X 4 Stainless Steel Weldolets to Pipe Welds ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ND-20-1220, Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan2020-10-21021 October 2020 Report of Changes Incorporated Into Revision 6 to the Security Plan, Training and Qualification Plan, and Safeguards Contingencv Plan ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20274A2582020-09-10010 September 2020 Wp on Uswc for AP1000_Revised, Reactor Oversight Process Whitepaper - Modification of the Description of Unplanned Scrams with Complications Performance Indicator to Reflect AP1000 Design ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ND-20-0561, Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report2020-07-10010 July 2020 Submittal of Turbine Maintenance and Inspection Program in Accordance with Updated Final Safety Analysis Report ML20189A4292020-07-0707 July 2020 Construction Reactor Oversight Process Resources July 2020 ML20136A4562020-04-30030 April 2020 Updated Flex Plan Nuclear Regulatory Commission Order EA-12-049 Strategies for Beyond Design Basis External Events NL-19-0832, EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections.2019-12-31031 December 2019 EPRI Technical Report 3002014590, Technical Bases for Inspection Requirements for PWR Steam Generator Feedwater and Main Steam Nozzle-to-Shell Welds and Nozzle Inside Radius Sections. ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) NL-19-0674, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-09-30030 September 2019 Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1 2024-01-08
[Table view] Category:Miscellaneous
MONTHYEARNL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error ML22348A0932023-07-28028 July 2023 Finding That the Acceptance Criteria in the Combined License Are Met ML23184A0472023-07-0303 July 2023 Dashboard Report 7-3-2023 ND-22-0831, (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 12022-10-31031 October 2022 (Vegp), Units 3 and 4, Comments on AP1000 Standard Technical Specifications (STS) Draft NUREG-2194, Revision 1 ML22215A0962022-08-0303 August 2022 Construction Reactor Oversight Process Resources Report August 3, 2022 ML22214A0072022-08-0101 August 2022 Archives ML22131A0502022-05-11011 May 2022 Construction Reactor Oversight Process Resources Report May 11, 2022 ND-21-1003, Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement2021-11-12012 November 2021 Request for Exemption: Applicability of 10 CFR 26.3. Scope, Until Initial Fuel Load - Supplement ND-21-0991, Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load2021-11-0505 November 2021 Exemption Request: Applicability of 10 CFR 26.3, Scope, Until Initial Fuel Load ML21280A3052021-10-0707 October 2021 Q/2020 Performance Summary ML21280A3042021-10-0707 October 2021 Q 2020 Performance Summary IR 05000424/20210052021-08-25025 August 2021 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 (Report 05000424/2021005 and 05000425/2021005) ND-21-0603, Electrical Construction and Measuring & Test Equipment Control2021-06-25025 June 2021 Electrical Construction and Measuring & Test Equipment Control ML20343A0672020-12-0202 December 2020 Dashboard Report 12-2-2020 ML20314A0492020-11-0909 November 2020 Construction Reactor Oversight Process Resources November 2020 ML20287A1862020-10-13013 October 2020 Construction Reactor Oversight Process Resources October 2020 ML20191A3832020-08-14014 August 2020 Transition to Reactor Oversight Process for Vogtle Electric Generating Plant, Units 3 and 4 ND-20-0907, Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1)2020-07-28028 July 2020 Revision to Proposed Alternative Requirements for Preservice Inspection Acceptance of Volumetric Examinations, in Accordance with 10 CFR 50.551(z)(1),(VEGP 3&4-PSI/ISI-ALT-14R1) ML19284B3722019-11-15015 November 2019 Attachment - VEGP U3 Amendment 166 (LAR-19-008) ND-18-1500, CFR 50.46 Thirty Day Report2018-12-18018 December 2018 CFR 50.46 Thirty Day Report ML18152B7852018-10-12012 October 2018 Summary of Nuclear Regulatory Commission Vendor Inspections Affecting Inspections, Tests, Analyses, and Acceptance Criteria ND-18-1047, Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule2018-08-0808 August 2018 Enclosure 2 - Redacted COL Operational Programs and Other License Conditions Implementation Schedule NL-18-0670, Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements2018-05-24024 May 2018 Third 10-Year Interval Inservice Inspection Program ISI Program Update: Notification of Impractical ASME Code Requirements NL-17-1889, NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information2017-12-0505 December 2017 NEI 12-06, Appendix H, Revision 4, H.4.5 Path 5: GMRS Greater than 2 X SSE, Mitigating Strategies Assessment (MSA) Report for the New Seismic Hazard Information NL-17-0777, Flooding Focused Evaluation Summary Report2017-06-30030 June 2017 Flooding Focused Evaluation Summary Report NL-17-0218, Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment2017-03-27027 March 2017 Fukushima Near-Term Task Force Recommendation 2.1: Seismic Probabilistic Risk Assessment NL-15-2276, Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20142015-12-23023 December 2015 Submittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2014 ML15106A3102015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Draft Minimum Shift Staffing Analysis ND-14-2009, 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample2014-12-17017 December 2014 4 - 10 CFR 26.719(c) Report: False Negative Results for a Blind Performance Test Sample NL-14-1899, Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20132014-12-0808 December 2014 Vogle, Units 1 and 2 - 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 ML14279A3522014-11-0606 November 2014 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML14169A5992014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14049A3542014-02-24024 February 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML13162A5342013-06-10010 June 2013 Initial Exam 2013-301 Final SRO Written Exam NL-13-0173, Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2013-02-27027 February 2013 Southern Nuclear Operating Company'S Overall Integrated Plan in Response to March 12,2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) NL-12-0324, Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-00062012-02-16016 February 2012 Special Report 2011-001-02, Inoperable Radiation Monitor 1RE-0006 NL-11-0626, Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-0062011-03-29029 March 2011 Special Report 2011-001-00, Inoperable Radiation Monitor 1RE-006 NL-10-1536, Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-0062010-08-18018 August 2010 Special Report 2010-001-00, Inoperable Radiation Monitor 1RE-006 ML1015903342010-06-0808 June 2010 Audit of Steam Generator H Amendment Reference Documents ML1019304172010-05-0606 May 2010 Tritium Database Report ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants NL-09-1449, Submittal of Emergency Response Data System (Eros) Data Point Library Modification2009-09-24024 September 2009 Submittal of Emergency Response Data System (Eros) Data Point Library Modification NL-09-1375, Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.102009-08-25025 August 2009 Enclosure 2 and 3 to NL-09-1375 - Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification (TS) Sections 5.5.9 and TS 5.6.10 NL-08-1405, Report of Unsatisfactory Performance Testing2008-09-12012 September 2008 Report of Unsatisfactory Performance Testing NL-08-0343, Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment2008-03-18018 March 2008 Response to NRC Request for Additional Information Relating to LTR-CDME-08-11 NP-Attachment NL-07-1777, Supplemental Response to NRC Generic Letter 2004-022008-02-28028 February 2008 Supplemental Response to NRC Generic Letter 2004-02 NL-08-0275, Response to 01/28/2008 Request for Additional Information2008-02-27027 February 2008 Response to 01/28/2008 Request for Additional Information ML0732405912007-11-0505 November 2007 Land Management Plan ML0732407392007-11-0505 November 2007 Stratigraphy and Depositional Environments of Sediments from Five Cores from Screven and Burke Counties, Georgia ML0732403812007-11-0505 November 2007 10 CFR 50.75(g) Leak/Spill Decommissioning Record, Figure 1, for 1980s and 1990s, NMP-EN-002, Version 1.0 2024-01-12
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Southern Nuclear Operating Company ND-20-0907 Enclosure Vogtle Electric Generating Plant(VEGP) Units 3 and 4 Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)- Requirements for Preservice inspection Acceptance of Volumetric Examinations (Enclosure consists of 8 pages, not including this cover page.)
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)-Requirements for Preservice Inspection Acceptance of Volumetric Examinations Plant Site-Vogtle Electric Generating Plant(VEGP)- Units 3 and 4 Unit:
interval- Applies to (1) preservice inspection and (2) the first period of the first interval Dates: inservice inspection (181) interval for reexamination of vessel welds.
Requested Date for Approval is requested by September 30, 2020, to support completion of preservice inspection activities prior to Unit 3 ITAAC completion.
Approval:
ASME Class 1 and Class 2 welds being examined during PSI using volumetric examination methods.
Class 1 applies to the reactor coolant system pressure boundary.
ASME Code Applicable welds are in Code Categories B-A, B-B, B-D, B-F, and B-J.
Components Class 2 applies to components that limit the leakage of radioactive material Affected: from the containment following a design basis accident. Applicable welds are in Code Categories C-A, C-B, C-C, C-F-1, and C-F-2.
The weld classes, weld categories, and non-destructive examination method for each weld are listed in the PSI program plan for each unit.
Applicable ASME Boiler & Pressure Vessel Code,Section III, 1998 Edition through Code Editions 2000 Addenda and Addenda: ASME B&PV Code,Section XI, 2007 Edition with the 2008 Addenda ASME Boiler & Pressure Vessel Code,Section III, 1998 Edition through 2000 Addenda NB-5280 Preservice Examination Applicable NB-5281 General Requirements Code (a) Examinations required by NCA-3252(c) shall be completed prior to Requirements: completion of the N-5 Data Report.
(b) All volumetric and surface examinations shall be documented with results and identified in a form consistent with those required in NCA-4134.17 for transfer to the Owner.
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)-Requirements for Preservice Inspection Acceptance of Volumetric Examinations NB-5282 Examination Requirements (a) Components shall be examined as specified in Section XI, Table IWB-2500-1. The method of examination for the components and parts of the pressure retaining boundaries shall comply with those tabulated in Table IWB-2500-1. Only the volumetric and surface examinations are required to be performed.
NB-5332 Preservice Examination (a) Components whose volumetric examination reveals flaws that meet the acceptance standards of Section XI, IWB-3000 shall be acceptable. The flaws will be dimensioned and recorded in accordance with Section V, Article 4 and this Subsection.
(b) Components whose volumetric examination reveals flaws that exceed the standards of IWB-3000 are not acceptable for service and shall be repaired.
ASME Boiler & Pressure Vessel Code,Section XI, 2007 Edition with the 2008 Addenda IWB-2200 Preservice Examination (a) Examinations required by this Article (with the exception of Examination Category B-P, and the visual VT-3 examination of the internal surfaces of Categories B-L-2 and B-M-2, of Table IWB-2500-1) shall be completed prior to initial plant startup. In addition, these preservice examinations shall be extended to include essentially 100% of the pressure retaining welds in all Class 1 components, except in those components exempted from examination by IWB-1220(a), (b), or (c). However, in the case of Examination Category B-0 (Table IWB-2500-1), the examination shall be extended to include essentially 100% of the welds in the installed peripheral control rod drive housings only.
(b)Shop and field examinations may serve in lieu of the on-site preservice examinations provided:
(1) in the case of vessels only, the examination is performed after the hydrostatic test required by Section III has been completed; (2)such examinations are conducted under conditions and with equipment and techniques equivalent to those that are expected to be employed for subsequent inservice examinations; (3)the shop and field examination records are, or can be, documented and identified in a form consistent with those required in IWA-6000.
(c) Steam generator tube examination shall be governed by the plant Technical Specification.
IWB-2500 Examination and Pressure Test Requirements
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)-Requirements for Preservice Inspection Acceptance of Volumetric Examinations (a) Components shall be examined and tested as specified in Table IWB-2500-1. The method of examination for the components and parts of the pressure retaining boundaries shall comply with those tabulated in Table IWB-2500-1 except where alternate examination methods are used that meet the requirements of IWA-2240.
IWB-3100 Evaluation of Examination Results IWB-3110 Preservice Volumetric and Surface Examinations IWB-3111 General (a) The preservice volumetric and surface examinations required by IWB-2200 and performed in accordance with IWA-2200 shall be evaluated by comparing the examination results with the acceptance standards specified in Table IWB-3410-1, except where IWB-3112(b) is applicable.
(b)Acceptance of components for service shall be in accordance with IWB-3112, IWB-3113, and IWB-3114.
IWB-3112 Acceptance (a) A component whose volumetric or surface examination either confirms the absence of or detects flaws that do not exceed the standards of Table IWB-3410-1 shall be acceptable for service, provided the verified flaws are recorded in accordance with the requirements of IWA- 1400(h), IWA-2220(b), and IWA-6230 in terms of location, size, shape, orientation, and distribution within the component.
(b) A component whose volumetric or surface examination (IWB-2200) detects flaws that meet the nondestructive examination standards of NB-2500 and NB-5300, as documented in Quality Assurance Records(NCA-4134.17), shall be acceptable.
(c) A component whose volumetric or surface examination (IWB-2200) detects flaws, other than the flaws of IWB-3112(b), that exceed the standards of Table IWB-3410-1 is unacceptable for service, unless the component is corrected by a repair /replacement activity to the extent necessary to meet the acceptance standards prior to placement of the component in service.
Additionally, IWC-3112 provides the commensurate requirements for Class 2 Components.
J PSI Ultrasonic Testing (UT) examinations may potentially identify indications that were not found by the ASME Section III Radiographic Testing (RT)
Reason for examinations or that do not meet the ASME Section XI PSI acceptance Request: standards. Limited use of ASME Section XI flaw evaluation methodology in
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSi/iSi-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)-Requirements for Preservice inspection Acceptance of Volumetric Examinations accordance with iWB-3600 and iWC-3600 will allow disposition of these indications without weld repairs that could be detrimental to the component.
The currently identified need for this alternative is based on indications detected in three Core Make-up Tank (GMT) inlet and outlet nozzle-to-head welds for Unit 3. This request is also provided based on the possibility that remaining PSI examinations could identify additional locations where flaw evaluation is needed for Vogtle Units 3 and 4.
As of May 27, 2020, the approximate number of Class 1 welds that are being examined using UT Preservice examination is 607 in each unit. For Unit 3, approximately 432 of these examinations have been completed, with about 175 remaining. The approximate total number of Class 2 welds that are being examined using UT Preservice examination is 128 in each unit. For Unit 3, approximately 49 of these examinations have been completed, with about 79 remaining.
Progress of PSI for Unit 3 substantially leads progress on Unit 4.
Proposed Alternative:
As an alternative to the requirements of ASME Section XI, 2007 Edition with 2008 Addenda, the requirements of ASME Section XI 2017 Edition Acceptance Standards, IWB-3112and IWC-3112, including Applicable Tables IWB- and IWC-3410-1 and referenced paragraphs, may be applied:
IWB-3112 Acceptance (a) A component whose volumetric or surface examination in accordance with IWB-2200 meets (1),(2), or(3) below shall be acceptable for service, provided the verified flaws are recorded in accordance with the requirements of IWA-1400(i) and IWA-2220(b) in terms of location, size, shape, orientation, and distribution within the component.
Proposed (1) The volumetric or surface examination confirms the absence of flaws or Alternative identifies only flaws that have already been shown to meet the and Basis nondestructive examination standards of NB-2500 or NB-5300, as documented in Quality Assurance Records(NCA-4134.17).
for Use:
(2) Volumetric examination detects flaws that are confirmed by surface or volumetric examination to be non-surface-connected and that do not exceed the standards of Table IWB-3410-1.
(3) Volumetric examination detects flaws that are confirmed by surface or volumetric examination to be non-surface-connected and that are accepted by analytical evaluation in accordance with the provisions of IWB-3132.3 to the end of the service lifetime of the component and reexamined in accordance with the requirements of IWB-2420(b) and IWB-2420(d).
(b) A component whose volumetric or surface examination detects flaws that do not meet the criteria established in (a) shall be unacceptable for service, unless the component is corrected by a repair/replacement activity in accordance with IWB-3113 to the extent necessary to meet the provisions of (a) prior to placement of the component in service.
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(2)(1)-Requirements for Preservice Inspection Acceptance of Volumetric Examinations (c) A component whose volumetric or surface examination (IWB-2200) detects flaws, other than the flaws of(b), that exceed the standards of Table IWB-3410-1 is unacceptable for service, unless the component is corrected by a repair/replacement activity to the extent necessary to meet the acceptance standards prior to placement of the component in service.
The following additional conditions shall be applied to welds accepted under ASME Section XI 2017 Edition IWB or IWC 3112(a)(3):
- This Alternative can be applied to a maximum of twelve (12) Class 1 welds and seven (7) Class 2 welds. These limits are applicable to each unit.
The total number of welds and initial individual flaw depth (T%)shall be limited to the following for each unit:
Maximum Code Class Number of T% < 50%* 50% < T% < 55%* 55% < T% < 60%
Welds Class 1 12 9 2 1 Class 2 7 4 2 1
- Unused weld count from higher depth limits can be used in these columns.
- The flaw evaluation shall demonstrate that the flaw is predicted to remain non-surface-connected for the entire service life of the component.
- Subsequent examination for each vessel weld that has been evaluated using this Alternative shall be conducted during the first inservice inspection (ISI) period.
Basis for Use:
The proposed alternative establishes that flaws, which are confirmed by surface or volumetric examination to be non-surface-connected and that are accepted by analytical evaluation in accordance with the provisions of IWB-3132.3 to the end of the service lifetime of the component, are acceptable.
IWB-3132.3 establishes the requirements for acceptance offlaws by analytical evaluation, as described in IWB-3600. This requirement for analytical evaluation of flaws is consistent with the requirements for flaws identified during inservice inspection. Therefore, the use of analytical flaw evaluation is an acceptable method to demonstrate weld integrity consistent with the requirements for operating nuclear plants. Hence, this alternative will provide an acceptable level of quality and safety, in accordance with 10 CFR 50.55a(z)(1).
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)-Requirements for Preservice Inspection Acceptance of Volumetric Examinations There are additional conditions proposed for the use of this alternative. These additional conditions establish the applicability of the alternative and limits for its use.
Specifically, the proposed alternative is applicable to a maximum of twelve(12)
Class 1 welds and seven (7) Class 2 welds. Also, the alternative is not applicable to the SG-to-RCP welds, which are fabricated component-to-component welds. These additional requirements for the overall use of the alternative are proposed to establish limits for use of analytical flaw evaluation for PSI. Limiting the total number of welds to twelve Class 1 and seven Class 2 in each unit is intended as a conservative limitation on the use of this alternative. These limits are less than 2% of Class 1 and 6% of Class 2 required welds being examined by UT for PSI. If additional application of analytical flaw evaluation is needed beyond these conservative limits, then it is intended that this restriction will assure that the process of accepting such evaluations is an iterative one, by requiring an additional request for alternative.
A requirement to conduct reexamination, in excess of the ASME Section XI 2017 Edition requirement, is also proposed. These subsequent examinations of vessel welds, to be performed during the first inservice inspection period, ensure that flaw evaluations for these vessel welds have adequately accounted for potential growth during startup and initial plant operation.
A limitation is proposed that the flaw evaluation shall demonstrate the flaw is predicted to remain non-surface-connected for the service life of the component. Also,the use of this alternative is limited to flaws with initial depths that do not exceed 60% of the wall thickness. IWB and IWC-3600 limit the depth offlaws to 75% for piping welds. For example, IWB-3644 states,"Flaws with depths greater than 75% of the wall thickness are unacceptable." The 75% depth limit identified in ASME Section XI has been previously accepted by the NRC for use in ISI as documented in 10 CFR 50.55a(a)(1)(ii). SNC's proposed initial flaw depth limit of 60% provides additional margin to the 75%
limit and will be applied to any weld that is subject to flaw evaluation under this proposed alternative. This limit, combined with the flaw evaluation prediction for flaw growth and subsequent reexamination of the welds, is expected to preserve the NRC-accepted ASME Section XI code 75% limitation during the service life of the components evaluated under this alternative.
Additional limitation on the number of welds that exceed 50% initial flaw depth is provided. Only two (2) of the welds are allowed in the range of 50% to 55%
maximum initial flaw depth. Only one (1) weld is allowed in the range of 55%
to 60% maximum initial flaw depth. The range category for the weld will be determined based on the maximum initial individual flaw size in that weld.
Additional flaws in that weld that exceed the IWB and IWC-3112 acceptance standards will also be considered during evaluations under this alternative.
The table of weld count limits for Class 1 and Class 2 provided above is modified by the note that states, "Unused weld count from higher depth limits can be used in these columns." This clarifies that unused weld counts for 6
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)-Requirements for Preservice inspection Acceptance of Volumetric Examinations higher depth limits can be used to allow evaluation of a lower depth limit. For example, if there are no welds in the 55% to 60% range, then there can be 3 welds evaluated in the 50% to 55% range.
The limitation on the number of welds that can be evaluated under this alternative further addresses uncertainty associated with the new design features and the low amount of operating experience of the API000, by limiting the total number of welds that can be evaluated under this alternative, in conjunction with limitation on applicability to initial flaw depth sizes. These limitations provide a form of risk-informed approach, by limiting the total number of welds that can be evaluated under this alternative and significantly limiting the number of welds with initial flaw depths that exceed 50%.
The subsequent IWB-3640 flaw evaluation will account for proximity of flaws, as described in ASME Section XI. For example, Nonmandatory Appendix C, C-2300 states, "For multiple adjacent flaws, when the shortest distance between the boundaries of two adjacent flaws is within the proximity limits specified in IWA-3300, the adjacent flaws shall be bounded by a single rectangular or circumferential planar area in accordance with IWA-3300."
The proposed additional limitations provide assurance that the use of this alternative will ensure that weld integrity is maintained and provide conservative limitations on the number of welds that can be subjected to flaw evaluation under IWB and IWC-3600. Also, it is noted that IWB-3640 states, "The procedures shall be the responsibility of the Owner and shall be provided to the regulatory authority having jurisdiction at the plant site." Therefore, this information will be available to the NRC, as required.
LIT methods being used during PSI ensure reliable flaw detection and characterization, as demonstrated by the detection of indications during PSI UT examination that were not found during ASME III RT exams. The fracture mechanics methods, which have been developed for use under the flaw evaluation methods described in ASME Section XI, allow for very accurate assessment of the impact of such flaws on the integrity of the structure.
Further, experience has shown that local repair of flaws can result in high residual stresses that can aggravate stress corrosion cracking. Studies have also shown that such weld repairs can reduce weld reliability, as compared to use of flaw evaluation techniques. This is highly relevant when considering repairs of embedded flaws in components welds, which often are larger thickness welds, as compared to piping system welds. In order to maintain the integrity of plant components, particularly fabricated vessels, the use of flaw evaluation with the conditions above, which includes the consideration of potential for flaw growth to become surface connected, and specific requirements for reexamination, establish the optimal conditions for maintaining weld integrity for the construction of Vogtle Units 3 and 4.
Therefore, the use of this alternative will provide an acceptable level of quality and safety, in accordance with 10 CFR 50.55a(z)(1).
ND-20-0907 Enclosure Revision to Proposed Alternative VEGP 3&4-PSI/ISI-ALT-14R1 in Accordance with 10 CFR 50.55a(z)(1)-Requirements for Preservice Inspection Acceptance of Volumetric Examinations Duration of Proposed PSI through the first period of the first 181 interval for reexamination.
Alternative:
Reference:
None Status: Awaiting NRC authorization