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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-22-0303, End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report2022-10-25025 October 2022 End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report RA-22-0178, End of Cycle 28 (M1R28) Inservice Inspection Summary Report2022-08-0808 August 2022 End of Cycle 28 (M1R28) Inservice Inspection Summary Report RA-19-0400, End of Cycle 27 (M1R27) Inservice Inspection Summary Report2021-01-19019 January 2021 End of Cycle 27 (M1R27) Inservice Inspection Summary Report RA-20-0031, Revision to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2020-01-23023 January 2020 Revision to Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-19-0341, Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2019-12-19019 December 2019 Request for Alternative in Accordance with 10 CFR 50.55a (z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-19-0268, End of Cycle 26 (M1 R26) Inservice Inspection Summary Report2019-07-10010 July 2019 End of Cycle 26 (M1 R26) Inservice Inspection Summary Report MNS-18-003, End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports2018-01-11011 January 2018 End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports MNS-17-033, Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval2017-08-0202 August 2017 Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval ML16208A0582016-07-14014 July 2016 End of Cycle 24 Inservice Inspection Report MNS-15-010, Inservice Inspection Report, End of Cycle 23 Refueling Outage2015-02-12012 February 2015 Inservice Inspection Report, End of Cycle 23 Refueling Outage ML14197A2872014-06-26026 June 2014 MISI-1462.10-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Plan, Enclosure 1 MNS-14-053, MISI-1462.20-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Pressure Test Plan2014-06-24024 June 2014 MISI-1462.20-0040, Revision 0, Fourth Inspection Interval Inservice Inspection Pressure Test Plan MNS-14-026, Risk-Informed Inservice Inspection Program Response to Request for Additional Information2014-03-0303 March 2014 Risk-Informed Inservice Inspection Program Response to Request for Additional Information ML13234A0692013-08-13013 August 2013 Relief Request Serial #13-MN-002, Risk-Informed Inservice Inspection Program Fourth Inservice Inspection Interval ML13212A0672013-07-22022 July 2013 Inservice Inspection Report End of Cycle 22 Refueling Outage ML13205A1692013-07-11011 July 2013 Steam Generator In-Service Inspection Summary Report Unit 1, End of Cycle (EOC)22 ML13078A0092013-02-27027 February 2013 Fourth Ten-Year Inservice Testing Interval Inservice Testing Program, Revision 28 ML12321A0502012-11-0101 November 2012 Steam Generator Inservice Inspection Report ML12025A1392012-01-12012 January 2012 Inservice Inspection Report End of Cycle 21 Refueling Outage ML11362A0792011-12-15015 December 2011 Fourth Inspection Interval Inservice Inspection Pressure Test Plan ML1025101862010-08-30030 August 2010 Relief Request Serial #10-MN-001 ML1020405152010-07-15015 July 2010 Inservice Inspection Report Unit 1, End of Cycle 20 Refueling Outage ML0918804232009-06-29029 June 2009 Relief Request Serial #09-MN-003 ML0918804242009-06-29029 June 2009 Relief Request Serial #09-MN-004 ML0905106612009-02-0909 February 2009 In-Service Inspection Report, Unit 1, End of Cycle (EOC) 19 ML0904908362009-02-0202 February 2009 Steam Generator In-Service Inspection Report, End of Cycle (EOC) 19 ML0805805772008-03-26026 March 2008 Relief, Third 10-Year Interval Inservice Inspection Program Plan Repair of Chemical Volume and Control System Valve 1NV-240, MD6274 ML0726204622007-08-23023 August 2007 Inservice Inspection Report, End of Cycle 18 Refueling Outage ML0704500202007-02-0808 February 2007 Notification of Inspection and Request for Information ML0617801652006-06-0909 June 2006 Inservice Testing Program, Request for Additional Information, Relief Request Nos. MC-GRP-01 ML0513003642005-05-0303 May 2005 Units 1 & 2, Inservice Testing Program Relief Request MC-SRP-NS-01 Supplement ML0508105992005-03-11011 March 2005 Duke Requests NRC Approval of an Alternative to the Requirements of the 1998 Edition Through the 2000 Addenda of the Pressure Vessel Code, Section XI for the Listed Inservice Inspection Intervals ML0423305882004-08-12012 August 2004 Third Ten-Year Inservice Testing Interval Inservice Testing Program, Revision 27 ML0421602882004-07-26026 July 2004 Relief Request (RR) 03-001 ML0419401702004-06-30030 June 2004 Inservice Inspection Report End of Cycle 16 Refueling Outage ML0407607472004-03-0808 March 2004 Inservice Inspection Plan Relief Requests ML0401505112004-01-0505 January 2004 Inservice Inspection (ISI) Pressure Test Plan, Third Ten-Year Interval Plan ML0400200412003-12-0909 December 2003 to Third Interval Inservice Inspection Plan, McGuire Nuclear Station, Units 1 and 2, Unit 1, Section 1 Through Unit 2, Section 2 ML0400200402003-12-0909 December 2003 to Third Interval Inservice Inspection Plan, McGuire Nuclear Station, Units 1 and 2, General Requirements Through Unit 1, Section 2 2022-08-08
[Table view] Category:Letter type:RA
MONTHYEARRA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-23-0295, Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval2024-01-0404 January 2024 Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0127, 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record2023-06-28028 June 2023 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023 Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations RA-23-0118, Cycle 29, Revision 1, Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) RA-23-0117, Report of Changes to Duke Energy McGuire Emergency Plan Annex2023-05-0101 May 2023 Report of Changes to Duke Energy McGuire Emergency Plan Annex RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023 Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46 RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023 Duke Energy Annual Radiological Environmental Operating Report - 2022 RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023 Annual Radioactive Effluent Release Report - 2022 RA-23-0037, Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis)2023-03-30030 March 2023 Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis) RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023 Onsite Property Insurance Coverage RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023 Biennial Decommissioning Financial Assurance Reports RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report2023-03-16016 March 2023 Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds2023-02-28028 February 2023 Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds RA-23-0065, Report of Changes to McGuire EAL Technical Basis Document2023-02-23023 February 2023 Report of Changes to McGuire EAL Technical Basis Document RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-17017 February 2023 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)2023-02-15015 February 2023 End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023 Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023 Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022 Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab RA-22-0312, Report of Changes to McGuire Emergency Plan Annex2022-10-26026 October 2022 Report of Changes to McGuire Emergency Plan Annex RA-22-0303, End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report2022-10-25025 October 2022 End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report RA-22-0291, Report of Changes to Emergency Plan Implementing Procedures2022-10-17017 October 2022 Report of Changes to Emergency Plan Implementing Procedures RA-22-0024, Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components2022-09-21021 September 2022 Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components RA-22-0253, Independent Spent Fuel Storage Installation (Isfsi), Register Use of Casks2022-08-25025 August 2022 Independent Spent Fuel Storage Installation (Isfsi), Register Use of Casks RA-22-0178, End of Cycle 28 (M1R28) Inservice Inspection Summary Report2022-08-0808 August 2022 End of Cycle 28 (M1R28) Inservice Inspection Summary Report RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022 Duke Energy Common Emergency Plan, Revision 2, Summary of Changes RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0149, Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-28028 April 2022 Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-22-0029, Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 20212022-04-27027 April 2022 Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 2021 RA-22-0127, Interim Part 21 Report of a Deviation or Failure to Comply for Cutler-Hammer Relay2022-04-0808 April 2022 Interim Part 21 Report of a Deviation or Failure to Comply for Cutler-Hammer Relay RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022 Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System 2024-01-08
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('-> DUKE Edward R. Pigott Site Vice President McGuire Nuclear Station ENERGY Duke Energy MG01VP I 12700 Hagers Ferry Road Huntersville. NC 28078 o: 980.875.4805 Edward. Pigott@duke-energy.com Serial: RA-23-0150 10 CFR 50.55a July 27, 2023 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 MCGUIRE NUCLEAR STATION, UNIT NO.2 DOCKET NO. 50-370 / RENEWED LICENSE NUMBER NPF-17
SUBJECT:
McGuire Nuclear Station Unit 2, End of Cycle 28 {M2R28) lnservice Inspection Summary Report Pursuant to the reporting requirements of American Society of Mechanical Engineers (ASME)
Section XI, as amended by ASME Code Case N-532-5, Duke Energy Carolinas, LLC (Duke Energy) hereby submits the lnservice Inspection Summary Report for the McGuire Unit 2 outage M2R28.
This submittal contains no regulatory commitments.
Should you have any questions concerning this letter, or require additional information, please contact Ryan Treadway - Director, Fleet Licensing, at (980) 373-5873.
Edward R. Pigott Site Vice President McGuire Nuclear Station
Enclosure:
- 1. lnservice Inspection Summary Report Unit 2 McGuire Spring 2023 Refueling Outage M2R28
U.S. Nuclear Regulatory Commission Page 2 Serial: RA-23-0150 cc: (with enclosure)
J. Klos, NRC Project Manager, NRR L. Dudes, NRC Regional Administrator, Region II C. Safouri, NRC Senior Resident Inspector
U.S. Nuclear Regulatory Commission Serial: RA-23-0150 RA-23-0150 Enclosure 1 Inservice Inspection Summary Report Unit 2 McGuire Spring 2023 Refueling Outage M2R28 (7 pages including this cover)
DUKE ENERGY INSERVICE INSPECTION
SUMMARY
REPORT Location: +DJHUV)HUU\5RDG
+XQWHUVYLOOH1RUWK&DUROLQD
NRC Docket No.
Commercial Service Date: 0DUFK
Owner: Duke Energy 526 South Church St.
Charlotte, NC 28201-1006 Revision 0 KASull1 Digitally signed by KASull1 (524967)
Kaitlyn Sullivan Originated By:
(524967) Date: 2023.07.12 09:11:06 -04'00' Date (PRINT NAME/SIGNATURE)
Digitally signed by E50268 (342024)
Checked By: Angela Staller Date: 2023.07.12 09:26:40
-04'00' Date (PRINT NAME/SIGNATURE)
Digitally signed by MAP9681 MAP9681 (102140)
Approved By: Mark Pyne (102140) Date: 2023.07.20 09:55:16
-04'00' Date (PRINT NAME/SIGNATURE)
FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number RA-23-0150 Plant McGuire Nuclear Station, 12700 Hagers Ferry Rd, Huntersville, NC 28078-9340 Unit No. 2 Commercial service date 3/01/1984 Refueling outage no. M2R28 (if applicable)
Current inspection interval Inservice Inspection: 4th Interval, Containment: 3rd Interval (1st, 2nd, 3rd, 4th, other)
Current inspection period Inservice Inspection: 3rd Interval, Containment: 3rd Interval (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the 2007 edition with 2008 addenda, 2017 edition (see inspection plans attachment), and 2019 edition (see attachment)
Date and revision of inspection plans See Attachment Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as above.
The following Code Cases are permitted by the ISI Plans: N-513-3, N-513-4, N-513-5, N-526, N-532-5, N-586-1, N-600, N-613-1, N-613-2, N-639, N-643-2, N-648-1, N-648-2, N-651, N-663, N-705, N-705-1, N-706-1, N-711-1, N-712, N-716, N-716-1, N-716-2, N-722-1, N-729-6, N-731, N-735, N-747, N-751, N-765, N-768, N-770-5, N-771, N-775, N-776, N-778, N-786-1, N-786-Code Cases used for inspection 3, N-798, N-800, N-805, N-809, N-823-1, N-825, N-831-1, N-843, N-845, N-and evaluation: 845-1, N-854, N-858, N-864, N-865, N-874, N-882, N-885, N-892 (if applicable, include cases modified by Case N-532 and later revisions)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of M2R28 conform to the requirements of Section XI.
(refueling outage number)
Digitally signed by KASull1 (524967)
Signed Date: 2023.07.12 10:08:49 -04'00' Date Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of North Carolina and employed by Bureau Veritas Inspection and Insurance Company of Lynn, MA have inspected the items described in this Owners Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Digitally signed by JFSwan (245816)
Jerome Swan $1,,6%XUHDX9HULWDV
,QVSHFWLRQDQG,QVXUDQFH Date: 2023.07.18 12:44:19
-04'00' Commissions I, N, NS, NSI, R Inspectors Signature National Board, State, Province, and Endorsements
ATTACHMENT McGuire Unit 2 End of Cycle 28 Inservice Inspection Report The McGuire Nuclear Station Unit 2 Fourth Ten Year Inservice Inspection (ISI) Plan complies with 10CFR50.55a(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda.
Per RIS 2004-12, Letter RA-20-0262, NRC Accession Number ML20260H325 and approval NRC Accession Number ML20300A206, the NRC staff concluded that the use of subparagraph IWA-4540(b) of the 2017 Edition of the ASME B&PV Code,Section XI, is acceptable for McGuire Unit 2.
Per RIS 2004-16, Letter RA-20-0263, NRC Accession Number ML20260H326 and approval NRC Accession Number ML21113A013, the NRC staff concluded that the use of subparagraph IWA-4340 of the 2017 Edition of the ASME B&PV Code,Section XI, is acceptable for McGuire Unit 2.
Per RIS 2004-12, Letter RA-20-0191, NRC Accession Number ML20265A028 and approval NRC Accession Number ML21029A335, the NRC staff concluded that the use of paragraphs IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 of the 2017 Edition of the ASME B&PV Code,Section XI, is acceptable for McGuire Unit 2.
Per RIS 2004-12, Letter RA-23-0001, NRC Accession Number ML20265A028 and approval NRC Accession Number ML21029A335, the NRC staff concluded that the use of paragraph IWA-6230 of the 2019 Edition of the ASME B&PV Code,Section XI, is acceptable for McGuire Unit 2.
This summary report is being submitted pursuant to the reporting requirements of ASME Section XI, IWA-6000 as amended by ASME Code Case N-532-5, Repair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Report Preparation and Submission Section XI, Division 1.
Contained within this summary report are the form OAR-1 (Owners Activity Report) and Tables 1 and 2 of Code Case N-532-5 for McGuire Nuclear Station during cycle 28 and Refueling Outage 28 (M2R28).
M2R28 is the second outage of the third ISI period in the fourth inspection interval. M2R28 is the second outage of the third Containment period in the third inspection interval. This report includes all Repair/Replacement activities from October 12th, 2021, through April 4th, 2023, cycle 28.
Date and Revision of Inservice Inspection Plans:
Fourth Interval Inservice Inspection Plans The following document comprises the McGuire Nuclear Station Fourth Interval Inservice Inspection Plan for Unit 2 (Class 1, 2, and 3 Components):
Fourth Interval Inservice Inspection Plan - McGuire Nuclear Station Units 1 and Unit 2, Document MISI-1462.10-0040-ISIPLAN, Rev 3, dated 06/23/2022.
Fourth Ten-Year Interval Inservice Inspection Schedule McGuire Nuclear Station Unit 2, Document MISI-1462,10-0040-U2 Schedule, Rev. 4, dated 07/06/2022.
The following document comprises the McGuire Nuclear Station Fourth Interval Inservice Inspection Pressure Test Plan for Unit 2:
McGuire Nuclear Station Fourth Inspection Interval Inservice Inspection Pressure Test Plan, Document MISI-1462.20-0040-PTPLAN, Rev 6, dated 02/15/2022.
Containment Inservice Inspection Plan The following document comprises the McGuire Nuclear Station Third Interval Containment Inservice Inspection Plan for Unit 2 (Class MC):
McGuire Nuclear Station - Third Interval Containment Inservice Inspection Plan - Containment
- Units 1 & 2, Document MC-ISIC3-1042-0001, Rev. 10, dated 09/06/2022.
Augmented ISI Plan The following document comprises the McGuire Nuclear Station Fourth Interval Augmented Inservice Inspection Plan and Schedule for Unit 2:
McGuire Nuclear Station - Fourth Interval Augmented Inservice Inspection Plan and Schedule, Document MISI-1462.10-0040AUGISI-U1&U2, Rev. 6, dated 02/12/2022.
CASE N-532-5 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description Boric acid residue found during the performance of the ASME Section XI required VT-2 visual examinations associated with the Class A Bolted Connections in Upper Containment was Relevant conditions identified in NCR performed per work order 20543582. During the 02462292 were evaluated by examination, the following as found boric acid Engineering and found to be leakage conditions were identified on valves acceptable.
2NC-31B, 2NC-35B, 2NC-53-FL1, and 2NC-53-FL2.
B-P, B15.10 Boric acid residue found during the performance of the ASME Section XI required VT-2 visual examinations associated with the ISI Class A Leakage Test evidence of leakage was identified on the following components: 2B, C, and D's Reactor Relevant conditions identified in NCR Coolant Pump (2NCPU0002, 2NCPU0003, 02467441 were evaluated by B-P, B15.10 2NCPU0004 respectively). Engineering and found to be acceptable.
Boric acid residue found during the performance of the ASME Section XI required VT-2 visual examinations associated with the ISI Class A Leakage Test evidence of leakage was identified on Relevant conditions identified in NCR the following RX Seal Table locations: B-6, H-2, B- 8, 02467437were evaluated by B-P, B15.10 D-8. Engineering and found to be acceptable.
ISI VT-3 Visual Examination of support 2MCA-SV- Relevant condition identified in NCR H55 was performed and during the examination, 02462368 were evaluated by the as found cold load setting of 1210# was Engineering and found to be acceptable.
observed. Design cold load setting is 1068# with +/- Additionally, the cold load setting was 10% range. Previous data was reviewed which had reset per the loads and tolerance given F-A, F1.20C acceptable as found cold load setting. by the specification documents.
The Visual Examination of the Primary Containment Moisture Barrier was performed as required by ASME Section XI, Subsection IWE. The examination identified relevant conditions of the moisture Relevant conditions identified in NCR barrier such as wear, damage, surface cracks, and 02462564 evaluated by Engineering and lack of adhesion that could permit intrusion of restored using corrective measures.
moisture against inaccessible areas of pressure retaining surfaces of the metallic containment shell E-A, E1.30 and insulation panels protecting the metallic shell.
ASME Section XI, ISI VT-3 Visual Examination of Primary Containment Leak Chase Channel Relevant conditions identified in NCR Enclosures was performed and during the 02462755 evaluated by Engineering to examination, it was identified that leak chase be acceptable for continued service and channel enclosure # 69 was missing the bronze electively restored.
E-A, E1.30 closure cover.
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CASE N-532-5 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Repair /
Code Replacement Class Item Description Description of Work Date Completed Plan Number Bolting Material 1 2NI-60 03/02/2023 20558798-01 Replaced Page 2 of 2