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Category:Letter type:ND
MONTHYEARND-24-0019, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2024-02-0101 February 2024 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0912, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2024-01-0202 January 2024 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0881, Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-12-0404 December 2023 Submittal of Vogtle Electric Generating Plant (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0817, (Vegp), Units 3 and 4 - Report of UFSAR Chapter 14 Changes to the Initial Test Program in Accordance with License Condition 2.D.(7)(a)2023-11-17017 November 2023 (Vegp), Units 3 and 4 - Report of UFSAR Chapter 14 Changes to the Initial Test Program in Accordance with License Condition 2.D.(7)(a) ND-23-0823, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-11-0303 November 2023 Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0723, (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-10-0404 October 2023 (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0697, (Vegp), Unit 4, Submittal of Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-09-0505 September 2023 (Vegp), Unit 4, Submittal of Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0669, (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule2023-08-0707 August 2023 (Vegp), Unit 4, Combined License (COL) Operational Programs and Other License Conditions Implementation Schedule ND-23-0205, (Vegp), Unit 3 - Combined License (COL) License Condition 2.D.(5)(d) Completion of Power Ascension Tests2023-07-28028 July 2023 (Vegp), Unit 3 - Combined License (COL) License Condition 2.D.(5)(d) Completion of Power Ascension Tests ND-23-0618, Resubmittal of ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.07c.ii.a (Index Number 797)2023-07-20020 July 2023 Resubmittal of ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.07c.ii.a (Index Number 797) ND-23-0609, Notification of Completion of All ITAAC2023-07-20020 July 2023 Notification of Completion of All ITAAC ND-23-0608, ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.03.03 (Index Number 72) ND-23-0607, ITAAC Closure Notification on Completion of ITAAC 2.1.02.02a (Index Number 13)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.02.02a (Index Number 13) ND-22-0796, ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813)2023-07-20020 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 3.3.00.08 (Index Number 813) ND-23-0459, ITAAC Closure Notification on Completion of ITAAC 2.6.01.04d (Index Number 587)2023-07-19019 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.01.04d (Index Number 587) ND-23-0162, ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165)2023-07-19019 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.03.05a.i (Index Number 165) ND-23-0575, ITAAC Closure Notification on Completion of ITAAC 2.6.01.04e (Index Number 588)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.01.04e (Index Number 588) ND-23-0439, ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.05.07a.i (Index Number 265) ND-23-0552, Southern Nuclear Operating Company, Vogtle Electric Generating Plant, Unit 4, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02c (Index Number 624)2023-07-18018 July 2023 Southern Nuclear Operating Company, Vogtle Electric Generating Plant, Unit 4, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02c (Index Number 624) ND-23-0483, ITAAC Closure Notification on Completion of ITAAC 2.1.01.04 (Index Number 4)2023-07-18018 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.1.01.04 (Index Number 4) ND-23-0586, ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159)2023-07-17017 July 2023 ITAAC Closure Notice on Completion of ITAAC 2.2.03.02a (Index Number 159) ND-23-0610, ITAAC Closure Notification on Completion of ITAAC Item 2.6.03.04c (Index Number 603)2023-07-17017 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.6.03.04c (Index Number 603) ND-23-0573, ITAAC Closure Notification on Completion of 2.4.02.02a (Index Number 497)2023-07-16016 July 2023 ITAAC Closure Notification on Completion of 2.4.02.02a (Index Number 497) ND-23-0406, ITAAC Closure Notification on Completion of ITAAC Item 2.4.02.02b (Index Number 498)2023-07-16016 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.4.02.02b (Index Number 498) ND-22-0816, ITAAC Closure Notification of Completion of ITAAC 2.1.02.05a (Index Number 19)2023-07-15015 July 2023 ITAAC Closure Notification of Completion of ITAAC 2.1.02.05a (Index Number 19) ND-23-0603, ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 3.5.00.06 (Index Number 831) ND-23-0446, ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.04.12a.iii (Index Number 250) ND-23-0594, ITAAC Closure Notification on Completion of ITAAC 2.6.05.02.ii (Index Number 629)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.05.02.ii (Index Number 629) ND-23-0601, ITAAC Closure Notification on Completion of ITAAC Item 2.7.05.02.i (Index Number 719)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.7.05.02.i (Index Number 719) ND-23-0606, ITAAC Closure Notification on Completion of ITAAC 2.5.04.02.i (Index Number 557)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.5.04.02.i (Index Number 557) ND-23-0476, ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.3.06.02a (Index Number 355) ND-23-0499, ITAAC Closure Notification on Completion of ITAAC 2.7.01.14 (Index Number 700)2023-07-15015 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.7.01.14 (Index Number 700) ND-23-0588, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.07.i (Index Number 78) ND-23-0121, ITAAC Closure Notification on Completion of ITAAC C.2.6.09.07 (Index Number 667)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC C.2.6.09.07 (Index Number 667) ND-23-0122, ITAAC Closure Notification on Completion of ITAAC C.2.6.09.08a (Index Number 668)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC C.2.6.09.08a (Index Number 668) ND-23-0597, ITAAC Closure Notification on Completion of ITAAC 2.5.02.06a.ii (Index Number 530)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.5.02.06a.ii (Index Number 530) ND-23-0002, ITAAC Closure Notification on Completion of ITAAC 2.2.05.07c (Index Number 270)2023-07-14014 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.05.07c (Index Number 270) ND-23-0111, ITAAC Closure Notification on Completion of ITAAC 2.6.09.05c (Index Number 646)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.09.05c (Index Number 646) ND-22-0980, ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.06.i (Index Number 75)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.1.03.06.i (Index Number 75) ND-23-0587, ITAAC Closure Notification on Completion of ITAAC 2.6.02.02c (Index Number 595)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.02.02c (Index Number 595) ND-23-0461, ITAAC Closure Notification on Completion of ITAAC 2.6.09.13a (Index Number 652)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.09.13a (Index Number 652) ND-23-0543, ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02a (Index Number 622)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.6.04.02a (Index Number 622) ND-23-0394, ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703)2023-07-13013 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.7.02.03a (Index Number 703) ND-23-0592, ITAAC Closure Notification on Completion of 2.7.06.03.i (Index Number 726)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of 2.7.06.03.i (Index Number 726) ND-23-0589, ITAAC Closure Notification on Completion of ITAAC 2.6.03.04a (Index Number 601)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.6.03.04a (Index Number 601) ND-23-0581, ITAAC Closure Notification on Completion of ITAAC 2.2.04.02a (Index Number 220)2023-07-12012 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.04.02a (Index Number 220) ND-23-0486, ITAAC Closure Notification on Completion of ITAAC 2.2.01.11a.iv (Index Number 117)2023-07-11011 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.2.01.11a.iv (Index Number 117) ND-23-0559, CFR26.719(c)(1) 30-Day Report for a Blind Sample Analysis Error2023-07-11011 July 2023 CFR26.719(c)(1) 30-Day Report for a Blind Sample Analysis Error ND-23-0443, ITAAC Closure Notification on Completion of ITAAC 2.3.10.07a.ii (Index Number 444)2023-07-0808 July 2023 ITAAC Closure Notification on Completion of ITAAC 2.3.10.07a.ii (Index Number 444) ND-23-0183, ITAAC Closure Notification on Completion of ITAAC Item 2.3.11.03b (Index Number 454)2023-07-0808 July 2023 ITAAC Closure Notification on Completion of ITAAC Item 2.3.11.03b (Index Number 454) 2024-02-01
[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:Technical
MONTHYEARML23325A2022024-01-16016 January 2024 CFR Part 52 Construction Lessons-Learned Report 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 ML22348A0882023-07-25025 July 2023 VEGP Unit 4 - 103g - Basis Document 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 ML22278A0382022-10-0505 October 2022 Dashboard Report 10-5-2022 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 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-21-0848, 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) ML21179A0972021-06-15015 June 2021 to Tier 1 ML21132A0482021-05-12012 May 2021 Construction Reactor Oversight Process Resources Report May 2021 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 ML21118A1162021-04-28028 April 2021 Emergency Response Data System (ERDS) Data Point Library for Vogtle Unit 3 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 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 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 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. 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 ND-19-0356, Pressurized Thermal Shock (PTS) Evaluation2019-04-10010 April 2019 Pressurized Thermal Shock (PTS) Evaluation ND-19-0665, (VEGP) Units 3 and 4 - WCAP-15927-NP, Design Process for AP1000 Common Q Safety Systems, Revision 7 (Public Version)2019-03-21021 March 2019 (VEGP) Units 3 and 4 - WCAP-15927-NP, Design Process for AP1000 Common Q Safety Systems, Revision 7 (Public Version) ML19038A4632019-02-0707 February 2019 Construction Reactor Oversight Process Resources ML18275A0402018-10-31031 October 2018 Technical Evaluation Report: Use of BADGER and Narwhal to Compute Strainer Failure Probability - Vogtle Units 1 and 2 Nuclear Power Plant NL-18-0684, Fukushima Near-Term Task Force Recommendation 2.1: Seismic Supplemental Information Regarding NEI 12-06. Appendix H. Revision 4. H.4.5 Path 5 Mitigating Strategies Assessment (MSA) Report2018-06-25025 June 2018 Fukushima Near-Term Task Force Recommendation 2.1: Seismic Supplemental Information Regarding NEI 12-06. Appendix H. Revision 4. H.4.5 Path 5 Mitigating Strategies Assessment (MSA) Report NL-14-0639, Revision 5 Pressure and Temperature Limits Report and Unit 2 Revision 5 Pressure and Temperature Limits Report2014-04-22022 April 2014 Revision 5 Pressure and Temperature Limits Report and Unit 2 Revision 5 Pressure and Temperature Limits Report NL-14-0344, Seismic Hazard and Screening Report for CEUS Sites2014-03-31031 March 2014 Seismic Hazard and Screening Report for CEUS Sites ML14043A4762014-02-24024 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 ML14006A2012014-01-0303 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Vogtle Electric Generating Plant, Units 1 and 2, TAC Nos.: MF0714 and MF0715 ML13211A2622013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 7 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 14 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 14 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 13 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 13 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 11 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 11 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 12 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 12 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 10 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 10 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 9 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 9 of 14 ML13211A2432013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 9 of 14 NL-13-1236, SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 6 of 142013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 6 of 14 ML13211A2602013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 5 of 14 ML13211A2592013-07-25025 July 2013 SNCV061-RPT-02, Ver. 2.0, Vogtle Unit 2 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic. Part 4 of 14 2024-01-08
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^ ,1 l. I I Michael J. Yox 7825 River Road
^OLlLn0rn lNLICl0dr Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel July 10, 2020 Docket No.: 52-025 52-026 ND-20-0561 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant - Units 3&4 Submittal of Turbine Maintenance and Inspection Program In Accordance with Updated Final Safety Analysis Report Ladies and Gentlemen:
This submission is made with regard to the Vogtle Electric Generating Plant(VEGP), Units 3&4 Combined License(COL) Number NPF-91 and NPF-92, as required by the VEGP 3&4 Updated Final Safety Analysis(UFSAR) Section 10.2.6, Combined License Information on Turbine Maintenance and Inspection. Per UFSAR Section 10.2.6, a turbine maintenance and inspection program will be submitted to the NRC staff for review prior to fuel load. The program will be consistent with the maintenance and inspection program plan activities and inspection intervals identified in UFSAR Subsection 10.2.3.6.
Southern Nuclear Operating Company(SNC) hereby submits the turbine maintenance and inspection program, provided in the enclosure, in accordance with UFSAR Section 10.2.6.
This letter contains no regulatory commitments.
Should you have questions regarding the enclosed information, please contact Kelli Roberts at (706) 848-6991.
Respectfully submitted.
Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
Vogtle Electric Generating Plant(VEGP) Units 3&4 Turbine Maintenance and Inspection Program MJY/LBP/sfr
U.S. Nuclear Regulatory Commission ND-20-0561 Page 2 of 3 go; Southern Nuclear Operatina Company / Georgia Power Company Mr. S. E. Kuczynski (w/o enclosures)
Mr. P. P. Sena III (w/o enclosures)
Mr. M. D. Meier (w/o enclosures)
Mr. D. H. Jones (w/o enclosures)
Mr. G. Chick Mr. M. Page Mr. P. Martino Mr. D. L. McKinney (w/o enclosures)
Mr. T. W. Yelverton (w/o enclosures)
Mr. B. H. Whitley Ms. C. A. Gayheart Ms. M. Ronnlund Mr. D. L. Fulton Mr. M. J. Vox Mr. C. T. Defnall Mr. J. Tupik Ms. S. Agee Mr. M. Humphrey Ms. A. C. Chamberlain Mr. S. Leighty Mr. N. Kellenberger Mr. E. Riffle Ms. K. Roberts Mr. J. Haswell Mr. D. T. BIythe Mr. K. Warren Mr. A. S. Parton Document Services RTYPE: VND.LI.LOO File AR.01.02.06 Nuclear Reaulatorv Commission Mr. W. Jones (w/o enclosures)
Mr. M. King (w/o enclosures)
Ms. M. Bailey w/o enclosures)
Mr. C. Patel Mr. C. Santos Mr. B. Kemker Mr. J. Eargle Mr. G. Khouri Ms. S. Temple Mr. C. J. Even Mr. A. Lerch Mr. S. Walker Mr. N.D. Karlovich Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic
U.S. Nuclear Regulatory Commission ND-20-0561 Page 3 of 3 Nuclear Regulatory Commission (Continued)
Mr. V. Hall Ms. K. P. Carrlngton Mr. M. Webb Mr. P.J. Heher State of Georgia Mr. R. Dunn Oalethorpe Power Corporation Mr. M. W. Price Ms. A. Whaley Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Mr. L. Oriani (w/o enclosures)
Mr. T. Rubenstein (w/o enclosures)
Mr. M. Corletti Mr. D. Hawkins Mr. J. Coward Other Mr. S. W. Kline, Bechtel Power Corporation Ms. L. A. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.
Mr. S. Roetger, Georgia Public Service Commission Ms. S. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. S. Blanton, Balch Bingham
U.S. Nuclear Regulatory Commission ND-20-0561 Enclosure Page 1 of 8 Southern Nuclear Operating Company ND-20-0561 Enclosure Vogtle Electric Generating Plant(VEGP) Units 3&4 Turbine Maintenance and Inspection Program
U.S. Nuclear Regulatory Commission ND-20-0561 Enclosure Page 2 of 8 a
COL Information on Turbine Maintenance and inspection per UFSAR Section 10.2.6 Per SNC's UFSAR Section 10.2.6, a turbine maintenance and inspection program will be submitted to the NRG staff for review prior to fuel load, and the program will be consistent with the maintenance and inspection program plan activities and inspection intervals identified in Subsection 10.2.3.6 (Reference 1). UFSAR section 10.2.6 also requires plant-specific turbine rotor test data and calculated toughness curves that support the material property assumptions in the turbine rotor analysis to be available for review after fabrication of the turbine and prior to fuel load. Plant specific rotor test data, material composition data, material testing validation, product quality certificates, and construction Quality Assurance(OA) records from the manufacturer are available for review in the final OA data packages(References 2 through 9).
Maintenance and Inspection Program Plan Requirements per UFSAR Section 10.2.3.6 Disassembly of the turbine is conducted during plant shutdown. Inspection activities include disassembly of the turbine conducted during plant shutdown and inspection of parts normally inaccessible when the turbine is assembled for operation. These activities are performed via Preventive Maintenance(PM)tasks (Attachment A)that are tracked in the site's asset management software database, MAXIMO.
At least one main steam stop valve, control valve, reheat stop valve, and intercept valve are dismantled and inspected approximately every 3 years during scheduled refueling or maintenance'shutdowns. A staggered inspection ensures that turbine valves are inspected every outage and that each group of valves, stop, control, or intercept, meets the 3-year inspection requirement. Attachment B shows the PM tasks associated with these inspections.
Main stop valves, control valves, reheat stop and intercept valves may be tested from the main control room with the turbine online using the turbine control and protection system (TOPS). The TOPS can control full or partial stroke of the valves. The control system contains test functions and allows for valves to be tested online. The reheat stop valves and intercept valves can be tested separately. All valve positions can be observed by operators in the control room. During a valve test, the other valves cannot be tested. Only one valve can be tested at a time (Reference 10).
Extraction nonreturn valves are tested prior to each startup per the Main Steam System normal operating procedure, 3-MSS-SOP-001 (Reference 11). As part of this procedure the nonreturn valve closing operation is tested and verified using surveillance procedure 3-MSS-NTS-20-001, Extraction Steam Power Assist Non-Return Valves Testing (Reference 13).
Turbine valve testing is performed at six-month intervals. The semi-annual testing frequency is based on nuclear industry experience that turbine-related tests are the most common cause of plant trips at power. A PM task will stroke test the valves listed on Attachment0 on a six (6) month frequency. Stroke testing is performed using 3-MTS-NTS-20-001, Main Turbine System Valve Stroke Test (Reference 12).
Extraction nonreturn valves are tested locally by stroking the valve full open with air, then equalizing air pressure, allowing the spring closure mechanism to close the valve. Closure of each valve is verified by direct observation of the valve arm movement. 3-MSS-SOP-001, Main Steam System normal operating procedure contains guidance for placing extraction steam into service (Reference 11). As part of this procedure the nonreturn valve closing operation is tested
U.S. Nuclear Regulatory Commission ND-20-0561 Enclosure Page 3 of 8 and verified using surveillance procedure, 3-MSS-NTS-20-001, Extraction Steam Power Assist Non-Return Valves Testing (Reference 13).
During outages, non-destructive examinations for the turbine assembly provide assurance that rotor flaws that lead to brittle fracture of a rotor are detected. These activities are performed via PM tasks (Attachment A)that are tracked in the site's asset management software database, MAXIMO.
Completion Statement Unit 4 procedures and PMs will be duplicated from Unit 3 procedures and PMs prior to initial fuel load in accordance with COL section 2.0.(12)(f)4. Based on the above information, SNC hereby notifies the NRC that the Turbine Maintenance and Inspection Plan criteria, as outlined in UFSAR sections 10.2.3.6 and 10.2.6, are met.
U.S. Nuclear Regulatory Commission ND-20-0561 Enclosure Page 4 of 8 References favailable for NRG inspection^
- 1. Updated Safety Analysis Report(UFSAR)Sections 10.2.3.6 and 10.2.6
- 2. SV3-MG01-VQQ-001, Final QA Data Package for Low Pressure Turbine A (Unit 3)
- 3. SV3-i\/iG01-VQQ-005, Final QA Data Package for High Pressure Turbine (Unit 3)
- 4. SV3-MG01-VQQ-007, Final QA Data Package for Low Pressure Turbine B (Unit 3)
- 5. SV3-MG01-VQQ-014, Final QA Data Package for Low Pressure Turbine C (Unit 3)
- 6. SV4-MG01-VQQ-002, Final QA Data Package for Low Pressure Turbine A (Unit 4)
- 7. SV4-MG01-VQQ-004, Final QA Data Package for Low Pressure Turbine B (Unit 4)
- 8. SV4-MG01-VQQ-013, Final QA Data Package for High Pressure Turbine (Unit 4)
- 9. SV4-MG01-VQQ-016, Final QA Data Package for Low Pressure Turbine 0(Unit 4)
- 10. API000 Main Turbine Control and Diagnostics System-System Specification Document, APP-TQS-M3-001
- 11. Main Steam System, 3-MSS-SQP-001
- 12. Main Turbine System Valve Stroke Test, 3-MTS-NTS-20-001
- 13. Extraction Steam Power Assist Non-Return Valves Testing, 3-MSS-NTS-20-001
U.S. Nuclear Regulatory Commission ND-20-0561 Enclosure Page 5 of 8 Attachment A High Pressure(HP)and Low Pressure(LP)Turbine PMs Tasks PM No. Title Component Work Scope/Task Content 3MTSPM0010 (90M-NEIL*) MTS- 3-MTS-MG-01 WORK SCOPE: HP -Inspection HP Turbine HP TURBINE INSPECTION TASK CONTENT:'Turbine Inspection should include the following:
Inspect Journal Bearings.
Inspect Thrust Bearing if disassembled during HP Inspection.
Inspect Oil Seals.
Inspect Packing.
Inspect Steam Path (nozzles, wheels, blade rings, rotors, diaphragms)
NDE rotor surface, blade/bucket attachment areas, and shaft bore (if applicable).
NDE/NDT should include visual exam, dye/fluorescent penetrant, magnetic particle, and Ultrasonic array testing as applicable.
Inspect Casing for erosion.
Inspect Packing & glands Inspect for evidence of rubbing (misalignment)
Inspect Casing, coupling, and Coupling Bolting.
Perform alignment during reassembly."
3MTSPM0076 (126M-NEIL)MTS- 3-MTS-MG-02A WORK SCOPE: Inspection-LP Turbine(Mono block. Welded, and Advanced Disk Design)
LP TURBINE A INSPECTION TASK CONTENT: -"Turbine Inspection should include the following:
Inspect Journal Bearings.
Inspect Thrust Bearing (if it is part of the LP).
Inspect Oil Seals.
Inspect Packing and glands.
Inspect Steam Path (nozzles, wheels, blade rings, rotors, and diaphragms)
NDE rotor surface, blade/bucket attachment areas, disc (if applicable) and shaft bore (if applicable).
NDE/NDT should include visual exam, dye/fluorescent penetrant, magnetic particle, and Ultrasonic array testing as applicable.
Perform Turning Gear inspection (as applicable to the individual rotor)
Inspect Casing for erosion.
Replace (as required) any turbine relief diaphragms Inspect for evidence of rubbing (misalignment)
Inspect Casing, Coupling, and Coupling Bolting.
Inspect Exhaust Hood Spray Piping and Nozzles for degradation Perform alignment during reassembly."
3MTSPM0077 (126M-NEIL)MTS- 3-MTS-MG-02B Same as 3-MTS-MG-02A above LP TURBINE B INSPECTION 3MTSPM0078 (126M-NEIL)MTS- 3-MTS-MG-02C Same as 3-MTS-MG-02A above LP TURBINE C INSPECTION Nuclear Electric Insurance Limited
U.S. Nuclear Regulatory Commission ND-20t0561 Enclosure Page 6 of 8 Attachment B Main Steam Stop / Control / Reheat Stop / Intercept Valve PM Tasks PM No. Title Component Activity 3MTSPM0012 (90M-NEIL*) MIS- 3-MTS-V001A Disassembled Inspection of Main Stop valves for evidence of MAIN TURBINE STOP 1 VALVE INSPECTION leakage,steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual 3MTSPM0015 (90M-NEIL) MTS- 3-MTS-V001B Disassembled Inspection of Main Stop valves for evidence of MAIN TURBINE STOP VALVE 3 INSPECTION leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0018 (90M-NEIL) MTS - 3-MTS-V002A Disassembled Inspection of Control (governor) valves for evidence MAIN TURBINE CONTROL VALVE 1 INSPECTION of leakage,steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0021 (90M-NEIL) MTS- 3-MTS-V002B Disassembled Inspection of Control (governor) valves for evidence MAIN TURBINE CONTROL VALVE 3 INSPECTION of leakage,steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0024 (90M-NEIL)MTS- 3-MTS-V003A Disassembled Inspection of Main Stop valves for evidence of MAIN TURBINE STOP VALVE 2 INSPECTION leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0027 (90M-NEIL) MTS- 3-MTS-V003B Disassembled Inspection of Main Stop valves for evidence of MAIN TURBINE STOP VALVE 4 INSPECTION leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0030 (90M-NEIL) MTS- 3-MTS-V004A Disassembled Inspection of Control (governor) valves for evidence MAIN TURBINE CONTROL VALVE 2 INSPECTION of leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
U.S. Nuclear Regulatory Commission ND-20-0561 Enclosure Page 7 of 8 PM No. Title Component Activity 3MTSPM0033 (90M-NEIL) MIS- 3-IVITS-V004B Disassembled Inspection of Control (governor) valves for evidence MAIN TURBINE CONTROL VALVE 4 INSPECTION of leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0036 (90M-NEIL) MTS- 3-MTS-V005A Disassembled Inspection of Reheat Intercept valves for evidence of MAIN TURBINE REHEAT STOP / INTERCEPT VAL VE A INSPECTION leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0039 (90M-NEIL) MTS- 3-MTS-V005B Disassembled Inspection of Reheat Intercept valves for evidence of MAIN TURBINE REHEAT STOP / INTERCEPT VAL VE B INSPECTION leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0042 (90M-NEIL) MTS- 3-MTS-V005C Disassembled Inspection of Reheat Intercept valves for evidence of MAIN TURBINE REHEAT STOP / INTERCEPT VAL VE C INSPECTION leakage,steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0045 {90M-NEIL) MTS- 3-MTS-V005D Disassembled Inspection of Reheat Intercept valves for evidence of MAIN TURBINE REHEAT STOP / INTERCEPT VAL VE D INSPECTION leakage,steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0048 (90M-NEIL) MTS - 3-MTS-V005E Disassembled Inspection of Reheat Intercept valves for evidence of MAIN TURBINE REHEAT STOP / INTERCEPT VAL VE E INSPECTION leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
3MTSPM0051 (90M-NEIL) MTS - 3-MTS-V005F Disassembled Inspection of Reheat Intercept valves for evidence of MAIN TURBINE REHEAT STOP / INTERCEPT VAL VE F INSPECTION leakage, steam cutting, cracks, excessive erosion, binding, etc.
Inspect valve per vendor recommendations in SV3-MG01-VM-004.
Disassembly and reassembly instructions are provided in manual.
Nuclear Electric Insurance Limited
U.S. Nuclear Regulatory Commission ND-20-0561 Enclosure Page 8 of 8 Attachment C Turbine Valve 6-Month Stroke Testing PM Task Title Component Activity 3MTSNTS20001 (6M) MIS - MAIN TURBINE 3-MTS-V001A, VALVE TEST 3-MTS-V001B, WORK INSTRUCTIONS: TEST VALVE 3-MTS-V002A, MOVEMENT FROM CONTROL ROOM USING 3-MTS-V002B, TOPS 3-MTS-V003A, 3-MTS-V003B, TECH SPEC NAME: VEGP34 UFSAR 10.2.3.6 3-MTS-V004A, 3-MTS-V004B, OUTAGE RELATED: No 3-MTS-V005A, 3-MTS-V005B, SPECIAL INSTRUCTIONS: Use Procedure# 3-3-MTS-V005C, MTS-NTS-20-001 3-MTS-V005D, 3-MTS-V005E, SPECIAL EQUIPMENT: None 3-MTS-V005F, 3-MTS-V006A, 3-MTS-V006B, 3-MTS-V006C, 3-MTS-V006D, 3-MTS-V006E, 3-MTS-V006F