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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report RA-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report RA-22-0021, Refuel 26 (C1 R26) Inservice Inspection (ISI) Report2022-01-26026 January 2022 Refuel 26 (C1 R26) Inservice Inspection (ISI) Report RA-21-0223, Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2021-08-0202 August 2021 Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0391, Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-12-19019 December 2019 Refuel 23 (C2R23) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report RA-19-0092, Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report2019-03-11011 March 2019 Refuel 24 (C1R24) Inservice Inspection (ISI) and Steam Generator Inspection (SG-ISI) Report CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-067, ASME OM Code In-Service Testing Program Document2016-08-31031 August 2016 ASME OM Code In-Service Testing Program Document CNS-16-042, Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval2016-06-13013 June 2016 Snubber Program Plan for the Fourth Ten-Year Inservice Testing Interval CNS-16-020, Inservice Inspection Report for End of Cycle 22 Refueling Outage2016-03-18018 March 2016 Inservice Inspection Report for End of Cycle 22 Refueling Outage ML15280A3422015-10-0505 October 2015 Fourth Inservice Inspection Interval Steam Generator Tube Plan ML15238A8832015-08-19019 August 2015 Fourth Inservice Inspection Interval Plan and Inservice Inspection Interval Pressure Test Plan CNS-15-074, CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related2015-08-13013 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A9002015-08-12012 August 2015 CISI-1462.10.0040, Revision 0, Fourth Interval Inservice Inspection Outage Schedule, Quality Assurance Program Related ML15238A8982015-08-12012 August 2015 CISI-1462.10.0040-ISI, Revision 1, Fourth Interval Inservice Inspection Plan CNS-15-061, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage2015-07-0606 July 2015 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 20 Refueling Outage ML15238A8962015-06-23023 June 2015 Fourth Inspection Interval Inservice Inspection Pressure Test Plan CNS-15-047, Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais)2015-05-15015 May 2015 Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage, Response to NRC Requests for Additional Information (Rais) CNS-15-022, Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities2015-03-16016 March 2015 Request to Use a Portion of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section Xl, for Inservice Inspection Activities CNS-14-105, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage2014-09-25025 September 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 21 Refueling Outage CNS-14-001, Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage2014-01-13013 January 2014 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 19 Refueling Outage ML13085A0252013-03-21021 March 2013 Inservice Inspection Report for End of Cycle 20 Refueling Outage ML12195A3462012-07-10010 July 2012 Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report for End of Cycle 18 Refueling Outage ML12125A2972012-05-0303 May 2012 Proposed Alternative Request Number 11-CN-001 for the Third Ten-Year Inservice Inspection Interval Response to NRC Request for Additional Information ML1109806012011-04-0505 April 2011 Steam Generator (SG) Tube Inspection Report for End of Cycle 17 Refueling Outage Pursuant to Technical Specification (TS) 5.6.8 ML1102003222011-01-19019 January 2011 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0920104982009-07-14014 July 2009 Inservice Inspection Report and Steam Generator In-Service Inspection Summary Report for End of Cycle 16 Refueling Outage ML0927500082008-09-11011 September 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 17 Refueling Outage ML0805001792008-02-11011 February 2008 Inservice Inspection Report and Steam Generator In-service Inspection Summary Report for End of Cycle 15 Refueling Outage ML0732001122007-11-0808 November 2007 Request for Relief Number 07-GO-001 Alloy 600 Pressurizer Weld Overlays - Submittal of Committed Information ML0721202212007-07-30030 July 2007 Notification of Inspection and Request for Information ML0713503782007-05-0707 May 2007 Submittal of Steam Generator Inservice Inspection Documentation for Third Ten-Year Interval ML0709502752007-03-28028 March 2007 Inservice Inspection Report for End of Cycle 16 Refueling Outage ML0623403632006-08-15015 August 2006 Inservice Testing (IST) Program for Pumps and Valves - Third Ten-Year Interval Plan ML0620603112006-07-18018 July 2006 Inservice Inspection Reports for End of Cycle 14 Refueling Outage ML0607403192006-03-0606 March 2006 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0603901542006-02-0606 February 2006 Notification of Inspection and Request for Information ML0525905642005-09-0808 September 2005 Request for Relief Number 05-CN-004 Limited Weld Examinations During End-of-Cycle 15 Refueling Outage ML0525004942005-08-30030 August 2005 Inservice Inspection Report and Steam Generator Outage Summary Report for End-of-Cycle 15 Refueling Outage ML0518601322005-06-16016 June 2005 Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan ML0514002732005-05-11011 May 2005 Request for Relief Number 05-CN-003, Limited Volumetric Inspection Coverages During End-of-Cycle 12 and End-of-Cycle 13 Refueling Outages 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 ML0502604532005-01-17017 January 2005 Inservice Inspection Report for End of Cycle 13 Refueling Outage ML0430103872004-10-19019 October 2004 Second Ten Year Inservice Inspection Interval Steam Generator C Hot Leg Nozzle Welds ML0414901162004-05-18018 May 2004 Request for Relief from Pressure Requirement at Certain Class 1 Inservice Inspection Pressure Test Boundaries ML0408502452004-03-17017 March 2004 Inservice Inspection Report for End-of- Cycle 14 Refueling Outage ML0317605962003-06-18018 June 2003 Inservice Inspection Report & Steam Generator Outage Summary Report for End of Cycle 12 Refueling Outage ML0313405102003-05-0707 May 2003 Relief, Request for Relief Number 02-002, Revision 1 Re Limited Weld Examinations for End of Cycle 13 Refueling Outage 2023-09-25
[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-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. 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-23-0288, End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report2023-11-16016 November 2023 End of Cycle 27 (C1 R27) Steam Generator Tube Inspection Report 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-23-0281, 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-23-0230, Refuel 27 (C1 R27) Inservice Inspection (ISI) Report2023-09-25025 September 2023 Refuel 27 (C1 R27) Inservice Inspection (ISI) Report 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-23-0215, Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks2023-08-28028 August 2023 Independent Spent Fuel Storage Installation (ISFSI) ISFSI Docket Number 72-45 Registration of Spent Fuel Storage Casks 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-18-0007, License Amendment Application to Revise Control Room Cooling Technical Specifications2023-06-19019 June 2023 License Amendment Application to Revise Control Room Cooling Technical Specifications 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-23-0105, Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core2023-05-0404 May 2023 Duke Energy Carolinas, LLC (Duke Energy) - Core Operating Limits Report (COLR) for Unit 1 Cycle 28 Reload Core 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-23-0042, Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change2023-04-24024 April 2023 Submittal of Updated Final Safety Analysis Report (Revision 23), Technical Specification Bases Revisions, Ufsar/Selected Licensee Commitment Changes, 10 CFR 50.59 Evaluation Summary Report, and Notification of a Commitment Change RA-23-0091, Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 42023-04-13013 April 2023 Submittal of Emergency Action Level (EAL) Technical Basis Document, Revision 4 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-23-0084, Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 42023-03-29029 March 2023 Core Operating Limits Report (COLR) for Unit 1 Cycle 27 Reload Core, Rev. 4 RA-23-0083, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 22023-03-16016 March 2023 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 2 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-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-22-0608, Refuel 25 (C2R25) Inservice Inspection (ISI) Report2023-01-25025 January 2023 Refuel 25 (C2R25) Inservice Inspection (ISI) Report 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-22-0331, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 12022-11-22022 November 2022 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core, Rev. 1 RA-22-0266, Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core2022-09-19019 September 2022 Core Operating Limits Report (COLR) for Unit 2 Cycle 26 Reload Core RA-22-0201, Refuel 24 Steam Generator Tube Inspection Report Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-07-21021 July 2022 Refuel 24 Steam Generator Tube Inspection Report Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections RA-22-0220, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks2022-07-19019 July 2022 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks RA-22-0218, Emergency Action Level (EAL) Technical Basis Document, Revision 32022-07-14014 July 2022 Emergency Action Level (EAL) Technical Basis Document, Revision 3 RA-22-0205, Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks2022-07-11011 July 2022 Independent Spent Fuel Storage Installation (Isfsi), Registration of Spent Fuel Storage Casks RA-22-0180, Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant2022-07-0707 July 2022 Supplement to Proposed Alternative to Use Reactor Vessel Head Penetration Embedded Flaw Repair for Life of Plant RA-22-0195, Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle2022-06-29029 June 2022 Response to Request for Additional Information (RAI) for the Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue for the Safety Injection Nozzle 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-22-0115, Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle2022-04-21021 April 2022 Request for Acceptance of Proposed Method to Manage Aging Due to Environmentally Assisted Fatigue (EAF) for the Safety Injection Nozzle 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 2024-01-10
[Table view] |
Text
Mandy Hare Nuclear Support Services Manager
~ ~ DUKE
~ ENERGY Duke Energy CN03CH I 4800 Concord Rd York, SC 29745 803. 701.2218 Mandy.Hare@duke-energy.com Serial: RA-22-0608 January 25, 2023 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Catawba Nuclear Station, Unit No. 2 Docket No. 50-414 I Renewed License No. NPF-52
Subject:
Catawba Unit 2, Refuel 25 (C2R25) lnservice Inspection (ISi) Report Ladies and Gentlemen:
In accordance with Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Duke Energy is providing its lnservice Inspection (ISi) Summary Report for Catawba Nuclear Station, Unit No. 2, Refuel 25 (C2R25).
The enclosure contains the C2R25 Owner's Activity Summary Report.
This submittal contains no regulatory commitments. Should you have any questions concerning this letter, or require additional information, please contact Ryan Treadway, Director - Nuclear Fleet Licensing, at 980-373-5873.
Sincerely,
~~ce.fhc Nuclear Support Services Manager, Catawba Nuclear Station
Enclosure:
Owner's Activity Summary Report For Refueling Outage 25 NOE
U.S. Nuclear Regulatory Commission Page 2 Serial: RA-22-0608 cc: (w/ enclosure)
S. Williams, NRC Project Manager, NRR L. Dudes, NRC Regional Administrator, Region II D. Rivard, NRC Senior Resident Inspector, Catawba Nuclear Station
Enclosure Serial: RA-22-0608 Enclosure Owners Activity Summary Report for Refueling Outage 25
DUKE ENERGY INSERVICE INSPECTION
SUMMARY
REPORT UNIT 2 CATAWBA FALL 2022 REFUELING OUTAGE C2R25 (Outage 5)
Location: 4800 Concord Road, York, SC, 29745 NRC Docket No. 50-414 Commercial Service Date: August 19, 1986 Owner: Duke Energy 526 South Church St.
Charlotte, NC 28201-1006 Revision 0 Digitally signed by ACKell1 (365600)
Date: 2023.01.18 08:38:28 -05'00' Originated By:
Austin C. Keller er Checked By:
Stephen L. L Mays ys Digitally signed by MAP9681 MAP9681 (102140) (102140)
Approved By: Date: 2023.01.18 14:28:43 -05'00' Mark A. Pyne
CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Owners Activity Report for Refueling Outage C2R25 Plant Catawba Nuclear Station, 4800 Concord Road, York, SC 29745 Unit No. 2 Commercial service date August 19, 1986 Refueling outage no. C2R25 (if applicable)
Current inspection interval Fourth Inspection Interval (ISI), Third Inspection Interval (Containment ISI)
(1st, 2nd, 3rd, 4th, other)
Current inspection period Second Inspection Period (ISI), Third Inspection Period (Containment ISI)
(1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the ASME Section XI 2007 Edition through 2008 inspection plans Addenda & 2017 Edition 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 Plan and Addenda:
4th Interval: N-513-3, N-532-5, N-586-1, N-600, N-613-1, N-639, N-643-2, N-648-2, N-651, N-705, N-706-1, N-712, N-716-1, N-722-1, N-729-6, N-731, N-735, N-747, N-751, N-765, N-770-5, N-771, N-775, N-776, Code Cases used for inspection N-786-1, N-798, N-800, N-805, N-823, N-825, N-843, N-845, N-854, &
and evaluation: N-885 (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 C2R25 conform to the requirements of Section XI.
(refueling outage number)
Digitally signed by ACKell1 (365600)
Date: 2023.01.18 08:38:59 Signed -05'00' Austin Keller, ISI Program Owner Date 01/18/2023 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 South 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 DMMalle (457903)
Date: 2023.01.19 10:27:36 -05'00' Commissions 15196 AI, IS, I, N, R; SC 363 Inspectors Signature National Board, State, Province, and Endorsements Dustin Mallet Date 01/19/2023 Page 1 of 5
CASE N-532-5 Attachment Catawba Unit 2 Refuel Outage 25, Inservice Inspection Report The Catawba Nuclear Station Unit 2 Fourth Ten Year Inservice Inspection (ISI) Plan complies with 10CFR50.55a(g), (79 FR 73462, Dec. 11, 2014), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda.
x 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 Catawba Unit 2.
x 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 Catawba Unit 2.
x 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 Catawba Unit 2.
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 Catawba Nuclear Station during cycle 25 and Refueling Outage 25 (C2R25).
C2R25 is the last outage of the second ISI period in the fourth inspection interval. C2R25 is the first outage of the third Containment period in the third inspection interval. This report reviewed all Repair/Replacement activities from May 4, 2021 through October 26, 2022, cycle 25.
Date and Revision of Inservice Inspection Plans:
I. Fourth Interval Inservice Inspection Plans
- 1. The following documents comprise the Catawba Nuclear Station 4th Interval Inservice Inspection Plan for Unit 2 (Class 1, 2, and 3 Components):
- a. Catawba Nuclear Station Units 1 and 2 Fourth Interval Inservice Inspection Plan, Document #CISI-1462.10-0040-ISI PLAN, Rev. 8, approved 03/08/2022.
- b. Fourth Interval Inservice Inspection Outage Schedule Catawba Nuclear Station Unit 2, Document #CISI-1462.10-0040-UNIT 2, Rev. 5, approved 03/08/2022.
- 2. The following documents comprise the Catawba Nuclear Station 4th Interval Inservice Inspection Pressure Test Plan for Unit 2:
- a. Catawba Nuclear Station Units 1 and 2 Fourth Inspection Interval Inservice Inspection Plan Pressure Test Plan, Document #CISI-1462.20.0040 - PTPlan, Rev. 4, approved 11/29/2021.
Page 2 of 5
CASE N-532-5 II. Fourth Interval Augmented Inservice Inspection Plan
- 1. The following document comprises the Catawba Nuclear Station 4th Interval Augmented Inservice Inspection Plan and Schedule for Unit 2:
- a. Augmented Inservice Inspection Plan and Schedule, Document #CISI-1462.10-0030-AUGISI-U1&U2, Rev. 8, approved 12/16/2021.
III. Third Interval Containment Inservice Inspection Plan
- 1. The following document comprises the Catawba Nuclear Station 3rd Interval Containment Inservice Inspection Plan for Unit 1 (Class MC):
- a. Catawba Nuclear Station Units 1 and 2 - Third Interval Containment Inservice Inspection Plan, Document #CN-ISIC3-1042-0001, Rev. 11, approved 07/13/2021.
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CASE N-532-5 TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number Dry, white inactive boric acid leakage was discovered on the 2A and 2D Reactor Boric acid residue found during ISI Coolant Pump Seal Area identified in B-P I B15.10 Pressure NCR #02446609. These relevant Test Zone, 2NC-001L-A conditions were evaluated by Engineering and found to be acceptable per IWA-5251 and IWB-3142.
The NDE examination of these closures showed no signs of degradation and were evaluated as acceptable by Engineering per IWE-3122.3. See NCR #02442184 for Boron was observed on leak chase E-A / E1.30 engineering evaluation. Work Request #
channel closures #26, #27, and #136.
020233360 was generated to clean and inspect the leak chase channel closures per TE-MN-PWR-0006. No degradation was noted after cleaning.
Evaluated by Engineering and accepted The horizontal sway struts mini clamps per IWF-3122.3. See NCR #02442050 for support 2-R-NC-1021 exhibited two and calculation CNC-1206.02-70-0073, loose nuts on the clamping device and F-A / F1.11 Rev. 17 for analysis of the as-found the vertical sway strut c-Clip locking condition. WR 20233293 was written to device was missing from the strut to mini restore the support to its original design clamp attachment locking pin.
configuration.
The legacy denting on the spring can housings was cosmetic and does not Multiple dents were observed on the affect the function of the spring or spring can housings for the Upper Air F-A / F1.40 support. The relevant condition was Lock barrel constant support 2-SUPT-evaluated by Engineering and accepted 0001.
per IWF-3122.3. See NCR #02442006 for engineering evaluation.
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CASE N-532-5 TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Repair /
Code Item Description Description of Work Date Completed Replacement Class Plan Number 2NC RX Head PT (RVCH) Nozzle #74 2RPV-Closure-Head- Embedded Flaw 1 Nozzle-74 Repair 10/14/2022 20479853-01 Page 5 of 5