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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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James M. Smith Manager - Nuclear Support Services McGuire Nuclear Station Duke Energy 12700 Hagers Ferry Rd Huntersville, NC 28078 980.875.5477 James-Junior.Smith@duke-energy.com Serial: RA-19-0400 10 CFR 50.55a January 19, 2021 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 MCGUIRE NUCLEAR STATION, UNIT NO.1 DOCKET NO. 50-369 / RENEWED LICENSE NUMBER NPF-9
SUBJECT:
McGuire Nuclear Station Unit 1, End of Cycle 27 (M1R27) Inservice 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 hereby submits the Inservice Inspection Summary Report for the McGuire Unit 1 outage M1R27.
This submittal contains no regulatory commitments.
Should you have any questions concerning this letter, or require additional information, please contact Art Zaremba, Manager - Nuclear Fleet Licensing, at 980-373-2062.
Sincerely, James M. Smith Manager - Nuclear Support Services, McGuire Nuclear Station Enclosure(s):
- 1. Inservice Inspection Summary Report - Unit 1 McGuire 2020 Refueling Outage M1R27 (4th Interval, Outage 6).
cc: (with enclosure)
J. Klos, NRC Project Manager, NRR L. Dudes, NRC Regional Administrator, Region II A. Hutto, NRC Senior Resident Inspector
U.S. Nuclear Regulatory Commission Serial: RA-19-0400 RA-19-0400 Enclosure 1 Inservice Inspection Summary Report - Unit 1 McGuire 2020 Refueling Outage M1R27 (4th Interval, Outage 6)
CASE N-532-5 FORM OAR-1 OWNERS ACTIVITY REPORT Report Number Owners Activity Report for Refueling Outage M1R27 Plant McGuire Nuclear Station, 12700 Hagers Ferry Rd, Huntersville, NC 28078-9340 Unit No. 1 Commercial Service Date 12/01/1981 Refueling Outage No. M1R27 (if applicable)
Current Inspection Interval ISI-4th, Containment-3rd (1st, 2nd, 3rd, 4th, other)
Current Inspection Period ISI-3rd, Containment-2nd (1st, 2nd, 3rd)
Edition and Addenda of Section XI Applicable to the Inspection Plans 2007 Edition with 2008 Addenda 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 inspection plans Code Cases Used The following Code Cases are permitted by the ISI Plans: N-513-4, N-526, N-532-5, N-586-1, N-600, N-613-1, for Inspection and N-613-2, N-639, N-643-2, N-648-1, N-648-2, N-651, N-705, N-706-1, N-712, N-716, N-722-1, N-729-4, N-731, Evaluation: N-735, N-747, N-765, N-770-2, N-771, N-775, N-776, N-786-1, N-798, N-800, N-823-1, N-825, N-843, N-845, and N-854.
(if applicable)
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 M1R27 conform to the requirements of Section XI.
(refueling outage number) 01/11/2021 Signed Date Jim Boughman, ISI Program Owner 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 OneCIS 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.
Jerome F Swan ANIIS OneCIS Insurance Commissions NB11473, NC1524; I, N, NS, NSI, R Inspectors Signature National Board, State, Province, and Endorsements Date 1-13-2021 Page 2 of 5
CASE N-532-5 ATTACHMENT McGuire Unit 1 End of Cycle 27 Inservice Inspection Report The McGuire Nuclear Station Unit 1 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.
This summary report is being submitted pursuant to the reporting requirements of ASME Section XI 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, Unit 1, during cycle 27 and Refueling Outage 27 (M1R27). M1R27 is the second and last outage of the third ISI period in the fourth inspection interval and the third outage of the second Containment period in the third inspection interval. This report includes all Repair/Replacement activities from April 16, 2019 through October 19, 2020, Cycle 27.
Date and Revision of Inservice Inspection Plans:
Fourth Interval Inservice Inspection Plans The following document comprises the McGuire Nuclear Station 4 th Interval Inservice Inspection Plan for Unit 1 (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 0, dated 04/30/2020.
Fourth Ten-Year Interval Inservice Inspection Schedule McGuire Nuclear Station Unit 2, Document MISI-1462.10-0040-Unit 2 Schedule, Rev. 0, dated 4/30/2020.
The following document comprises the McGuire Nuclear Station 4th Interval Inservice Inspection Pressure Test Plan for Unit 1:
McGuire Nuclear Station Fourth Inspection Interval Inservice Inspection Pressure Test Plan, Document MISI-1462.20-0040-PTPLAN, Rev 4, dated 11/10/2020.
Containment Inservice Inspection Plan The following document comprises the McGuire Nuclear Station 3rd Interval Containment Inservice Inspection Plan for Unit 1 (Class MC):
McGuire Nuclear Station - Third Interval Containment Inservice Inspection Plan - Containment -
Units 1 & 2, Document #MC-ISIC3-1042-0001, Rev. 7, dated 06/06/2019.
Augmented ISI Plan The following document comprises the McGuire Nuclear Station 4th Interval Augmented Inservice Inspection Plan and Schedule for Unit 1:
McGuire Nuclear Station Fourth Interval Augmented Inservice Inspection Plan and Schedule, Document MISI-1462.10-0040AUGISI-U1&U2, Rev. 5, dated 12/11/2019.
Page 3 of 5
CASE N-532-5 McGuire Nuclear Unit 1 Form OAR-1 Owners Activity Report Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number Component evaluated per IWF-3122.3 by Relevant Condition discovered on Hydraulic Snubber 1-F-A / F1.20C Engineering and found to be acceptable. NCR#
MCA-ND-H304 02348983.
Component evaluated per IWF-3112.3 by Relevant Condition discovered on Feedwater Storage F-A / F1.40 Engineering and found to be acceptable. NCR#
Tank Support 02348667 Component evaluated per IWB-3142.4 and Relevant Condition discovered on 1A Reactor Coolant B-P / B15.10 IWA-5250 by Engineering and found to be Pump acceptable. NCR# 02353917 Components evaluated per IWB-3142.4 and B-P / B15.10 Relevant Condition discovered on valve 1ND-1B IWA-5250 by Engineering and found to be acceptable. NCR# 02349386 Relevant Condition discovered on valve 1NV-87 and Accepted by Corrective Measures NCR#
C-H / C7.10 1FWTX-5050 02285128 and Work Order# 01814202 Components evaluated per IWC-3132.3 and Relevant Condition discovered on valve 1NV-227 and C-H / C7.10 IWA-5250 by Engineering and found to be 1A Centrifugal Charging Pump acceptable. NCR# 02309424 Component evaluated per IWC-3132.3 and C-H / C7.10 Relevant Condition discovered on valve 1ND-35 IWA-5250 by Engineering and found to be acceptable. NCR# 02340821 Component evaluated per IWC-3132.3 and C-H / C7.10 Relevant condition found on valve 1NI-183B IWA-5250 by Engineering and found to be acceptable. NCR# 02346466 Component evaluated per IWC-3132.3 and C-H / C7.10 Relevant condition found on valve 1ND-18 IWA-5250 by Engineering and found to be acceptable. NCR# 02346463 Accepted by Corrective Measures NCR#
C-H / C7.10 Relevant condition found on valve 1NV-491 02279746 and Work Order# 02199064 Components evaluated per IWC-3132.3 and D-B / D2.10 Relevant Condition discovered on valve 1KF-20 IWA-5250 by Engineering and found to be acceptable. NCR# 02338128 Components evaluated per IWC-3132.3 and D-B / D2.10 Relevant Condition discovered on valve 1KF-11 IWA-5250 by Engineering and found to be acceptable. NCR# 02336390 Component evaluated per IWC-3132.3 and D-B / D2.10 Relevant Condition discovered on valve 1KF-31 IWA-5250 by Engineering and found to be acceptable. NCR# 02349130 Component evaluated per IWC-3132.3 and D-B / D2.10 Relevant Condition discovered on valve 1KF-23 IWA-5250 by Engineering and found to be acceptable. NCR# 02349130 Nuclear Service Water piping examinations performed Components were evaluated for continued R-A/R1.17 in accordance with Category R-A, Item R1.17 for service by Engineering and found to be localized corrosion acceptable. AR 02351620.
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CASE N-532-5 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Repair / Replacement Item Description Description of Work Date Completed Class Plan Number None Page 5 of 5