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EPID:L-2022-LRO-0141, End of Cycle 27 (M2R27) Steam Generator Tube Inspection Report (Approved, Closed) |
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Category:Inspection Report
MONTHYEARIR 05000369/20240032024-11-0404 November 2024 Integrated Inspection Report 05000369/2024003 and 05000370/2024003 IR 05000369/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection – U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20234012023-08-0404 August 2023 – Security Baseline Inspection Report 05000369/2023401 and 05000370/2023401 (OUO-SRI) Cover IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 – Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station – Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 IR 05000369/20220012022-04-23023 April 2022 Integrated Inspection Report 05000369/2022001 and 05000370/2022001 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 IR 05000369/20224022022-03-24024 March 2022 Security Baseline Inspection Report 05000369/2022402 and 05000370/2022402 IR 05000369/20210062022-03-0202 March 2022 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 (Report 05000369/2021006 and 05000370/2021006) IR 05000369/20220102022-02-16016 February 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000369/2022010 and 05000370/2022010 IR 05000369/20210042022-01-26026 January 2022 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2021004 and 05000370/2021004 ML21342A3862021-12-0707 December 2021 William B. McGuire Nuclear Plant - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection (NRC Inspection Report 05000369/2022401 and 05000370/2022401) IR 05000369/20210032021-10-28028 October 2021 Integrated Inspection Report 05000369/2021003 and 05000370/2021003 IR 05000369/20210052021-08-23023 August 2021 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2 (NRC Inspection Report 05000369/2021005 and 05000370/2021005) IR 05000369/20210022021-08-0303 August 2021 Integrated Inspection Report 05000369/2021002 and 05000370/2021002 IR 05000369/20214012021-07-30030 July 2021 Security Baseline Inspection Report 05000369/2021401 and 05000370/2021401 IR 05000369/20210112021-05-20020 May 2021 Triennial Fire Protection Inspection Report 05000369/2021011 and 05000370/2021011 IR 05000369/20214022021-05-20020 May 2021 Security Baseline Target Set Inspection Report 05000369/2021402 and 05000370/2021402 IR 07200038/20210012021-04-30030 April 2021 Construction of an Independent Spent Fuel Storage Installation Report 07200038/2021001 IR 05000369/20210012021-04-30030 April 2021 Integrated Inspection Report 05000369/2021001 and 05000370/2021001 IR 05000369/20210102021-03-17017 March 2021 Design Basis Assurance Inspection Teams Inspection Report 05000369 2021010 and 05000370/2021010 2024-08-26
[Table view] Category:Letter type:RA
MONTHYEARRA-24-0254, Resubmittal of Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components2024-10-14014 October 2024 Resubmittal of Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components RA-24-0185, Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-16182024-08-28028 August 2024 Snubber Program Plan - Snubber Program Plan Revision, AD-EG-MNS-1618 RA-24-0193, Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-08-28028 August 2024 Supplement to Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2) RA-24-0137, Relief Requests for Inservice Testing Plan – Fifth Interval2024-07-0101 July 2024 Relief Requests for Inservice Testing Plan – Fifth Interval RA-24-0030, Duke Energy - Annual Radioactive Effluent Release Report - 20232024-04-29029 April 2024 Duke Energy - Annual Radioactive Effluent Release Report - 2023 RA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-24-0031, Annual Radiological Environmental Operating Report - 20232024-04-23023 April 2024 Annual Radiological Environmental Operating Report - 2023 RA-24-0094, Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Traini2024-04-17017 April 2024 Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Training RA-24-0101, (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency2024-04-16016 April 2024 (Mns), Units 1 and 2, Notification of Deviation from MRP-227, Revision 1-A Baffle-to-Former Bolt Inspection Frequency RA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations RA-24-0085, Onsite Property Insurance Coverage2024-04-0101 April 2024 Onsite Property Insurance Coverage RA-24-0086, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-04-0101 April 2024 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-24-0067, Independent Spent Fuel Storage Installation (ISFSI)2024-02-29029 February 2024 Independent Spent Fuel Storage Installation (ISFSI) RA-24-0004, End of Cycle 29 (M1R29) Inservice Inspection Summary Report2024-02-21021 February 2024 End of Cycle 29 (M1R29) Inservice Inspection Summary Report RA-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-23-0297, Transmittal of the Duke Energy Corporation Topical Report (Duke QAPD-001-A), Amendments 48, 49 and 502023-11-15015 November 2023 Transmittal of the Duke Energy Corporation Topical Report (Duke QAPD-001-A), Amendments 48, 49 and 50 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-23-0117, 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 2024-08-28
[Table view] |
Text
Edward R. Pigott DUKE Site Vice President d_
McGuire Nuclear Station ENERGY Duke Energy MG01VP j 12700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4111 Edward.Pigott@duke-energy.com Serial: RA-22-0101 10 CFR 50.4 March 24, 2022 10 CFR 50.36(c)(5)
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 27 (M2R27) Steam Generator Tube Inspection Report Ladies and Gentlemen:
In accordance with McGuire Nuclear Station (MNS) Technical Specification 5.6.8, "Steam Generator Tube Inspection Report," Duke Energy Carolinas, LLC (Duke Energy) is providing the steam generator tube inspection summary report for the MNS Unit 2, Refueling Outage 27 (M2R27). The report is provided as the Enclosure to this letter.
This submittal contains no regulatory commitments.
Should you have any questions concerning this letter, or require additional information, please contact Mr. Lee Grzeck, Nuclear Fleet Licensing Manager (Acting), at 980-373-1530.
Sincerely,
Edward R. Pigott Site Vice President McGuire Nuclear Station
Enclosure:
Steam Generator Tube Inspection Summary Report, McGuire Unit 2, M2R27 (Fall Refueling Outage 2021) cc: (with enclosure)
J. Klos, NRC Project Manager, NRR L. Dudes, NRC Regional Administrator, Region 11 A. Hutto, NRC Senior Resident Inspector
U.S. Nuclear Regulatory Commission Serial: RA-22-0101 Enclosure RA-22-0101 Enclosure Steam Generator Tube Inspection Summary Report, McGuire Unit 2, M2R27 (Fall Refueling Outage 2021)
McGuire 2 EOC-27 Steam Generator Tube Inspection Report Pursuant to McGuire technical specification 5.6.8 and industry guidance the following information is provided:
Background
McGuire Nuclear Station utilizes a Recirculating Steam Generator (SG) design for primary to secondary heat transfer. There are four steam generators per unit, with reactor coolant flow divided among the four. The McGuire RSGs are Model CFR80, manufactured by Babcock and Wilcox Canada and were replaced at EOC 11 in 1997. Each steam generator has 6,633 tubes constructed of thermally treated Inconel Alloy 690 (I-690) with an outside diameter of 0.688 inches and nominal wall thickness of 0.040 inches. The tubes are hydraulically expanded full depth of the tubesheet, complete from the primary to secondary face, and flush seal welded at the primary face.
On the secondary side, the tubes are supported using lattice grids and U-Bend restraints (commonly referred to as fanbars). There are 9 lattice grid tube support plates arranged vertically along the SG above the tubesheet. There are 8 fanbars per steam generator. They are arranged in a fan-shaped orientation, connected by connector bars. Figure 1 provides a visual representation of the of the SGs.
McGuire has a feedwater equalization header that also functions as a foreign object trapping device by its design.
No deviations have been taken from industry guidelines.
The nominal Thot is ~615 degrees Fahrenheit.
McGuire has implemented a measurement uncertainty uprate.
There has been no detectable primary to secondary leakage since the last inspection at EOC-24.
Report
- a. The scope of inspections performed on each SG.
Bobbin Inspection
- Full length of 100% of the in-service tubes.
Array Inspection
- 100% of periphery tubes (5 tubes in from periphery) with array probe from top of tubesheet to the first support in both hot leg (TSH to 01H) and cold leg (TSC to 01C).
- Special interest inspections were also performed on selected indications.
o 100% of all bobbin I-codes, PRX, and PLP.
Primary Visual Inspections
- Previously installed plugs
- Bowl cladding inspections Secondary Side Inspections
- Foreign object search and retrieval (FOSAR) of the tubesheet in all 4 steam generators
- Visual inspection of the upper most lattice grid in 2A SG only
- Visual inspection of the steam drum in 2A SG only o Laser metrology of selected secondary separator bottom plates
- b. The nondestructive examination techniques utilized for tubes with increased degradation susceptibility.
There are no tubes with increased degradation susceptibility.
- c. For each degradation mechanism found:
- 1. The nondestructive examination techniques utilized.
The bobbin probe was utilized for the detection of wear at support structures, freespan locations and to size wear at support structures. The array probe was used to size the foreign object wear.
- 2. The location, orientation (if linear), measured size (if available), and voltage response for each indication. For tube wear at support structures less than 20 percent through-wall, only the total number of indications needs to be reported.
There were 350 indications of fanbar (FB) wear reported. Twenty-five (25) of these indications were newly reported. The deepest of fanbar wear indication was 29% TW. The average growth rate was near zero. The largest 95th percentile growth rate among all SG is 0.7%TW/EFPY.
There were sixteen (16) indications of lattice grid (LG) wear reported. Four (4) of these indications were newly reported. The deepest of lattice grid wear indication was 11% TW. The average growth rate for lattice grid wear was near zero. The maximum growth rate for repeat indications was 0.78%TW/EFPY. There were two (2) indications of foreign object (FO) wear reported. Both were historical and showed no growth. The two FO wear indications were reported as HNC.
The complete listing for indications greater than or equal to 20%TW is attached.
- 3. A description of the condition monitoring assessment and results, including the margin to the tube integrity performance criteria and comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment.
The cumulative SG EFPY for EOC-24 was 17.62, EOC-25 was 19.01, EOC-26 was 20.44 and EOC-27 was 21.84. The last inspection was at EOC-24.
As of EOC-27, the McGuire Unit 2 steam generators had operated 20.64 EFPY since the first in-service inspection after replacement. In total, the McGuire Unit 2 steam generators had operated 21.84 EFPY since replacement.
Condition monitoring structural and leakage integrity were met for fanbar, lattice grid and foreign object wear.
An NDE maximum depth call of 49.1 %TW or less for fanbar wear is sufficient to demonstrate a minimum degraded tube burst pressure of 3P, 4050 psi, at 0.95 probability with 50%
confidence. The worst case depth call for fanbar wear observed during the inspection was an NDE depth of 29%TW.
An NDE maximum depth call of 51.4 %TW or less for lattice grid wear is sufficient to demonstrate a minimum degraded tube burst pressure of 3P, 4050 psi, at 0.95 probability with 50% confidence. The worst case depth call for lattice grid wear observed during the inspection was an NDE depth of 11%TW.
An NDE maximum depth call of 51.9%TW or less for FO wear is sufficient to demonstrate a minimum degraded tube burst pressure of 3P, 4050 psi, at 0.95 probability with 50%
confidence. The worst case depth call for FO wear observed during the inspection was an NDE depth of 15%TW.
The table below shows the comparison with the margin predicted to exist at the inspection by the previous forward-looking tube integrity assessment to the current as found degradation Degradation EOC-27 Projection (%TW) EOC-27 As Found (%TW)
FB Wear Maximum Depth (Repeat) 41.3 29 FB Wear Maximum Depth (New) 39.0 14 LG Wear Maximum Depth (Repeat) 28.6 11 LG Wear Maximum Depth (New) 35.9 11 FO Wear Maximum Depth <54.3 15 No degradation was detected in the plug visual or bowl cladding inspections.
No in-situ tests or tube pulls were performed.
- 4. The number of tubes plugged [or repaired] during the inspection outage.
There were no tubes plugged during the EOC-27 inspection outage.
- d. An analysis summary of the tube integrity conditions predicted to exist at the next scheduled inspection (the forward-looking tube integrity assessment) relative to the applicable performance criteria, including the analysis methodology, inputs, and results.
The operational assessment was determined deterministically for the worst case flaw.
Degradation Maximum depth projected OA Limit Growth rate Projected EFPY at next inspection (%TW) (%TW/EFPY)
(%TW)
FB Wear 47.4 52 1.6 7.3 LG Wear 30 54.3 1.6 7.3 For FO wear, since conditional monitoring was met and there is no mechanism for future growth then tube integrity is expected to be met at the next inspection.
- e. The number and percentage of tubes plugged [or repaired] to date, and the effective plugging percentage in each SG.
Steam Generator1 2A 2B 2C 2D Total Prior to EOC-27 26 8 18 10 62 EOC-27 0 0 0 0 0 Total 26 8 18 10 62
% Plugged/Effective Plugging (%) 0.39 0.12 0.27 0.15 0.23 1= There are 6633 tubes per steam generator
- f. The results of any SG secondary side inspections.
During FOSAR, a total of 28 metal objects were found with 18 removed. All foreign objects that were not removed have a technical evaluation demonstrating that tube integrity will be met through the next scheduled inspection at EOC31. There was no wear associated with any foreign object.
An examination of the upper-most (9th) lattice grid support was performed in 2A SG. The examination was performed via an inspection port above the 9th lattice grid and included several inner bundle passes and a drop-down inspection to the top of the 5th lattice grid. The purpose was to assess the material condition and cleanliness of this region of the SG. No evidence of degradation was identified. Deposit loading on the tube and structure surfaces, and within lattice openings, was relatively minor in the regions examined.
Visual examinations were also performed in the 2A SG steam drum to assess the material condition of the subcomponents in this region. The primary and secondary separators were of particular interest due to FAC susceptibility of the materials in these components and a history of FAC in the secondary separators.
In addition to the visual examinations, laser metrology was performed to trend the remaining thickness of the secondary separator bottom plates.
These examinations confirmed that secondary separator skimmer wall FAC is continuing. A total of 59 separators were identified with throughwall degradation as compared with 43 during the EOC-25 outage.
It appears that portions of the skimmer wall are flaking off and migrating to the tube bundle at the secondary face of the tubesheet. Secondary separator bottom plate FAC is continuing although no throughwall penetration was identified. The maximum material loss was measured to be approximately 95% as compared with 48% (returned to service) at the EOC-25 outage. In addition, five stiffener plates in two primary separator curved arms were identified as degraded by FAC; a condition not previously observed in the SGs.
Sludge lancing removed various materials, comprised mostly of gasket material, sludge flakes, graphite pieces, thin metallic strips, and a few pieces of wires, springs and metal shavings and weld slag/splatter and approximately 162.5 pounds of sludge. The thin metallic strips found in each SG had a unique scalloped surface on one side consistent with flow accelerated corrosion (FAC) that is suspected of being secondary moisture separator material and are evaluated as not expecting to cause wear that would exceed the structural limit over the next 4 cycles (5.85 EFPY).
Sludge Lancing removed 162.5 pounds of sludge total with 42 pounds removed form 2A SG, 25 pounds removed from the 2B SG, 42.5 pounds removed from the 2C SG and 53 pounds removed from the 2D SG.
Approximately 7800 pounds of iron are contained in the four steam generators by iron transport.
Figure 1 - CFR80 Elevation Map FB 4 FB 5 CFR 80 Tube Information:
No. of Tubes 6633 CBH CBC Material: Inconel 690 Nominal Dia.: 0.688 09H 09C Nominal Wall: 0.040 Tube Support Information Type: Lattice 08H 08C Material: Ferritic SS Fan Bar (FB)
Material: Ferritic SS 07H 07C Collector Bar (CB)
Material: Ferritic SS 06H 06C 05H 05C 04H 04C 03H 03C 02H 02C 01H 01C TSH TSC TEH TEC
List of indications greater than or equal to 20%TW McGuire 2, EOC-27
SG - 2A Attachment - Indications greater than or eqial 20% TW McGuire 2 2EOC27 MNS 20210901 01/20/2022 12:24:15
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l 2021/09/01 111 70 .85 276 PCT 26 P5 FB5 .65 TEC TEH .560 ZBAHS 12 H 293 WAR l l 2021/09/01 111 70 .60 91 PCT 21 P5 FB6 1.68 TEC TEH .560 ZBAHS 12 H 293 WAR l l l l 2021/09/01 86 73 .69 269 PCT 23 P5 FB5 -1.01 TEC TEH .560 ZBAHS 8 H 176 WAR l l l l 2021/09/01 117 76 .57 292 PCT 20 P5 FB3 .95 TEC TEH .560 ZBAHS 8 H 124 WAR l l 2021/09/01 117 76 .78 280 PCT 25 P5 FB5 -1.20 TEC TEH .560 ZBAHS 8 H 124 WAR l l l l 2021/09/01 115 78 .57 98 PCT 20 P5 FB6 -1.54 TEC TEH .560 ZBAHS 9 H 73 WAR l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
Tubes: 4 Records: 6 1 ST Max
SG - 2B Attachment - Indications greater than or eqial 20% TW McGuire 2 2EOC27 MNS 20210901 01/20/2022 12:24:14
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
Tubes: 0 Records: 0 1 ST Max
SG - 2C Attachment - Indications greater than or eqial 20% TW McGuire 2 2EOC27 MNS 20210901 01/20/2022 12:24:14
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l 2021/09/01 80 67 .73 91 PCT 24 P5 FB5 1.22 TEC TEH .560 ZBAHS 21 H 30 WAR l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
Tubes: 1 Records: 1 1 ST Max
SG - 2D Attachment - Indications greater than or eqial 20% TW McGuire 2 2EOC27 MNS 20210901 01/20/2022 12:24:15
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l 2021/09/01 108 69 .98 269 PCT 29 P5 FB4 1.33 TEC TEH .560 ZBAHS 5 H 296 WAR l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
l INSPDATE ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2 UTIL3l
+-----------+----+----+---------+----+----+----+-----+----+---------+---------+----+----+------+------+------+--+-----+---------+---------+---------+
Tubes: 1 Records: 1 1 ST Max