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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARRA-23-0011, End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report2023-01-26026 January 2023 End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report RA-22-0172, Duke Energy Progress, LLC - Supplement to Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval2022-06-10010 June 2022 Duke Energy Progress, LLC - Supplement to Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval RA-21-0200, End of Cycle 23 (H1R23) Inservice Inspection Program Owner'S Activity Report2021-08-11011 August 2021 End of Cycle 23 (H1R23) Inservice Inspection Program Owner'S Activity Report RA-21-0067, Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval2021-02-25025 February 2021 Response to Request for Additional Information - Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection Program, Fourth Ten-Year Interval RA-20-0082, Submittal of 180-Day Steam Generator Tube Inspection Report2020-04-0808 April 2020 Submittal of 180-Day Steam Generator Tube Inspection Report RA-20-0025, Cycle 22 Owner'S Activity Report2020-02-12012 February 2020 Cycle 22 Owner'S Activity Report RA-19-0206, Proposed Alternative for the Third 10-Year Inservice Inspection Program2019-04-30030 April 2019 Proposed Alternative for the Third 10-Year Inservice Inspection Program RA-18-0066, Cycle 21 Owner'S Activity Report2018-07-31031 July 2018 Cycle 21 Owner'S Activity Report HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-16-092, Relief Request I3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval2016-10-19019 October 2016 Relief Request I3R-16, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Third Ten-Year Interval HNP-15-064, Submits 90-day Inservice Inspection Summary Report2015-08-0505 August 2015 Submits 90-day Inservice Inspection Summary Report HNP-15-037, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique, Response to Request for Additional Information2015-04-24024 April 2015 Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique, Response to Request for Additional Information HNP-15-034, Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval2015-04-15015 April 2015 Relief Request I3R-15 Revision and Supplement, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program - Third Ten-Year Interval HNP-15-010, Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval2015-04-0202 April 2015 Relief Request I3R-15, Reactor Vessel Closure Head Nozzle Repair Technique Inservice Inspection Program - Third Ten-Year Interval HNP-14-099, Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information2014-09-0808 September 2014 Relief Request I3R-14, Deferral of Reactor Vessel Inspections Inservice Inspection Program - Third Ten-Year Interval Response to Request for Additional Information HNP-13-119, Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval2013-11-22022 November 2013 Relief Request I3R-13, Reactor Vessel Closure Head Nozzle 37, Inservice Inspection Program - Third Ten-Year Interval HNP-13-071, Day Inservice Inspection Summary Report Corrections2013-06-26026 June 2013 Day Inservice Inspection Summary Report Corrections HNP-13-057, Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Lnservice Inspection Program - Third Interval2013-05-22022 May 2013 Relief Request I3R-11 Reactor Vessel Closure Head Nozzles Lnservice Inspection Program - Third Interval HNP-12-091, Day Inservice Inspection Summary Report2012-09-0505 September 2012 Day Inservice Inspection Summary Report HNP-12-018, Day Inservice Inspection (ISI) Summary Report Corrections2012-04-11011 April 2012 Day Inservice Inspection (ISI) Summary Report Corrections HNP-11-045, 180-Day Steam Generator Tube Inspection Report2011-05-0505 May 2011 180-Day Steam Generator Tube Inspection Report HNP-11-017, 90-Day Inservice Inspection (ISI) Summary Report2011-02-10010 February 2011 90-Day Inservice Inspection (ISI) Summary Report HNP-09-095, Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program2009-09-24024 September 2009 Response to Request for Additional Information Regarding Relief Requests 2R1-018, 2R1-019, 2R1-020, 2R1-021, 2R1-022, 2R2-009, 2R2-010, & 2R2-011 for the Second 10-Year Inservice Inspection Program ML0923103532009-08-27027 August 2009 Correction to 10-Year Inservice Inspection Interval Enumerated in Relief Request 13R-02 Issued on April 30, 2009 HNP-09-076, 90-Day Inservice Inspection (ISI) Summary Report2009-08-0606 August 2009 90-Day Inservice Inspection (ISI) Summary Report HNP-08-067, Supplement to Third Interval Inservice Inspection Relief Request 13R-02 Submittal2008-06-19019 June 2008 Supplement to Third Interval Inservice Inspection Relief Request 13R-02 Submittal ML0804600932008-02-0808 February 2008 RFO13 90 Day Inservice Inspection (ISI) Summary Report ML0813304642008-01-30030 January 2008 Rev. 0 to PEN02.G03, Shearon Harris Nuclear Plant ISI Program Plan, Third 10-Year Inspection Interval. Cover to Page 8-2 ML0813304652008-01-30030 January 2008 Rev. 0 to PEN02.G03, Shearon Harris Nuclear Plant ISI Program Plan, Third 10-Year Inspection Interval. Attachment 1: Welds & Supports Schedule ML0813304662008-01-30030 January 2008 Rev. 0 to PEN02.G03, Shearon Harris Nuclear Plant ISI Program Plan, Third 10-Year Inspection Interval. Page 288 to End HNP-07-179, 90-Day Inservice Inspection (ISI) Summary Report2008-01-18018 January 2008 90-Day Inservice Inspection (ISI) Summary Report HNP-07-145, Inservice Inspection Relief Request 1, Summary of Ultrasonic Examinations of Preemptive Weld Overlays for Pressurizer Nozzle Locations Containing Alloy 600 Materials2007-10-22022 October 2007 Inservice Inspection Relief Request 1, Summary of Ultrasonic Examinations of Preemptive Weld Overlays for Pressurizer Nozzle Locations Containing Alloy 600 Materials HNP-07-143, Inservice Inspection Relief Request 1 Re Weld Overlay Repair Stress Analysis Summary2007-10-19019 October 2007 Inservice Inspection Relief Request 1 Re Weld Overlay Repair Stress Analysis Summary HNP-07-042, Revision of the Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan2007-03-22022 March 2007 Revision of the Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan HNP-06-141, Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan2006-12-18018 December 2006 Relief Request from ASME OM Code Inservice Testing Requirements for the Third Ten-Year Interval Plan HNP-06-091, Relief Requests from ASME Code Inservice Testing Requirements to Allow Online Disassembly of Certain Check Valves2006-09-0707 September 2006 Relief Requests from ASME Code Inservice Testing Requirements to Allow Online Disassembly of Certain Check Valves HNP-06-081, Submittal of Inservice Inspection Summary Report for Harris Nuclear Plant2006-08-10010 August 2006 Submittal of Inservice Inspection Summary Report for Harris Nuclear Plant HNP-05-088, One-Year Special Report - Steam Generator Tube Inservice Inspection Results2005-08-0101 August 2005 One-Year Special Report - Steam Generator Tube Inservice Inspection Results HNP-05-018, Inservice Inspection Summary Report2005-02-15015 February 2005 Inservice Inspection Summary Report HNP-04-076, One Year Special Report, Steam Generator Tube Inspection Results2004-05-0707 May 2004 One Year Special Report, Steam Generator Tube Inspection Results HNP-03-081, Inservice Inspection Summary Report2003-08-13013 August 2003 Inservice Inspection Summary Report HNP-02-051, Part 2 of 2, Shearon Harris Nuclear Power Plant, Inservice Inspection Summary Report, Class 2 Through End2002-04-0101 April 2002 Part 2 of 2, Shearon Harris Nuclear Power Plant, Inservice Inspection Summary Report, Class 2 Through End HNP-01-170, Inservice Inspection Summary Report for Harris Nuclear Plant2002-01-24024 January 2002 Inservice Inspection Summary Report for Harris Nuclear Plant 2023-01-26
[Table view] Category:Letter type:RA
MONTHYEARRA-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-24-0006, 10 CFR 50.54(q) Evaluation2024-01-0404 January 2024 10 CFR 50.54(q) Evaluation 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-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific2023-11-0606 November 2023 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific 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-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2023-09-21021 September 2023 Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals 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-23-0195, Notice of Intentions Regarding Apparent Violation Response; (EA-23-060)2023-07-20020 July 2023 Notice of Intentions Regarding Apparent Violation Response; (EA-23-060) 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-23-0135, 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-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023 License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications 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-23-0044, 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-23-0098, Annual Environmental (Nonradiological) Operating Report2023-04-19019 April 2023 Annual Environmental (Nonradiological) Operating Report 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-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-22-0081, License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications2023-02-0707 February 2023 License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications 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-23-0011, End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity Report2023-01-26026 January 2023 End of Cycle 24 (H1R24) Inservice Inspection Program Owner'S Activity 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-22-0314, Notification of Source Water Resiliency and Response Plan Submission2022-11-0202 November 2022 Notification of Source Water Resiliency and Response Plan Submission RA-22-0297, Cycle 25 Core Operating Limits Report, Revisions 0 and 12022-10-17017 October 2022 Cycle 25 Core Operating Limits Report, Revisions 0 and 1 RA-22-0214, 10 CFR 50.54(Q) Review Form for Revisions to the Shearon Harris Nuclear Power Plant, Unit 1, Emergency Action Level (EAL) Technical Basis Document and the EAL Wallchart Document2022-07-12012 July 2022 10 CFR 50.54(Q) Review Form for Revisions to the Shearon Harris Nuclear Power Plant, Unit 1, Emergency Action Level (EAL) Technical Basis Document and the EAL Wallchart Document RA-22-0197, Reactor and Senior Reactor Operator Initial Examinations 05000400/20223012022-07-0606 July 2022 Reactor and Senior Reactor Operator Initial Examinations 05000400/2022301 RA-22-0213, Notification of Modification to Permit Application for Industrial Stormwater Activities2022-06-30030 June 2022 Notification of Modification to Permit Application for Industrial Stormwater Activities RA-22-0172, Duke Energy Progress, LLC - Supplement to Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval2022-06-10010 June 2022 Duke Energy Progress, LLC - Supplement to Relief Request HNP-IST-004-RR1 for Inservice Testing Program Plan - Fourth Ten-Year Interval 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-22-0136, Annual Environmental (Nonradiological) Operating Report2022-04-29029 April 2022 Annual Environmental (Nonradiological) Operating Report 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-22-0028, 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-22-0117, Relief Request for Inservice Testing Program Plan - Fourth Ten-Year Interval2022-04-0707 April 2022 Relief Request for Inservice Testing Program Plan - Fourth Ten-Year Interval RA-22-0114, Duke Energy Carolinas, LLC and Duke Energy Progress, LLC Submittal of 10CFR26.719(c)(1) Report of Unsatisfactory Performance of Health and Human Services Certified Laboratory2022-04-0101 April 2022 Duke Energy Carolinas, LLC and Duke Energy Progress, LLC Submittal of 10CFR26.719(c)(1) Report of Unsatisfactory Performance of Health and Human Services Certified Laboratory RA-22-0014, Duke Energy Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations2022-03-21021 March 2022 Duke Energy Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations RA-22-0079, Snubber Program Plan2022-02-28028 February 2022 Snubber Program Plan RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-22-0055, Evacuation Time Estimate Report2022-02-18018 February 2022 Evacuation Time Estimate Report RA-22-0043, CFR 50.54(q) Evaluation2022-02-0808 February 2022 CFR 50.54(q) Evaluation RA-22-0037, Emergency Plan Annex, Revision 1 and Emergency Plan Annex, Revision 1, Emergency Action Level (EAL) Wallchart, Revision 2, and EAL Technical Basis Document2022-02-0808 February 2022 Emergency Plan Annex, Revision 1 and Emergency Plan Annex, Revision 1, Emergency Action Level (EAL) Wallchart, Revision 2, and EAL Technical Basis Document 2024-01-08
[Table view] |
Text
Kevin P. Riley
( ~ DUKE Nuclear Support Services Manager ENERGY. Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 984 229.2124 10 CFR 50.4 April 8, 2020 Serial: RA-20-0082 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington , DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Subject; 180-Day Steam Generator Tube Inspection Report Ladies and Gentlemen:
In accordance with the Technical Specifications (TS) of Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Duke Energy Progress, LLC, submits the attached 180-Day Steam Generator Inspection Report for HNP. This report has been prepared in accordance with TS 6.9.1.7, "Steam Generator Tube Inspection Report," and provides the complete results of HNP Refueling Outage No. 22.
This letter contains no new regulatory commitments.
Please address any questions regardrng this matter to Dennis Earp at 984-229-2673.
Sincerely, Kevin P. Riley
Enclosure:
180-Day Steam Generator Tube Inspection Report cc: J. Zeiler, NRG Sr. Resident Inspector, HNP T. Hood, NRG Project Manager, HNP L. Dudes, NRG Regional Administrator, Region II
Kevin P. Riley Nuclear Support Services Manager Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 984.229.2124 10 CFR 50.4 April 8, 2020 Serial: RA-20-0082 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63
Subject:
180-Day Steam Generator Tube Inspection Report Ladies and Gentlemen:
In accordance with the Technical Specifications (TS) of Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Duke Energy Progress, LLC, submits the attached 180-Day Steam Generator Inspection Report for HNP. This report has been prepared in accordance with TS 6.9.1.7, Steam Generator Tube Inspection Report, and provides the complete results of HNP Refueling Outage No. 22.
This letter contains no new regulatory commitments.
Please address any questions regarding this matter to Dennis Earp at 984-229-2673.
Sincerely, Kevin P. Riley
Enclosure:
180-Day Steam Generator Tube Inspection Report cc: J. Zeiler, NRC Sr. Resident Inspector, HNP T. Hood, NRC Project Manager, HNP L. Dudes, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission HNP-20-0082 Enclosure SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 Enclosure 180-Day Steam Generator Tube Inspection Report (6 pages including cover)
Harris Nuclear Plant HNP1 RFO122 Steam Generator Tube Inspection Report Pursuant to Harris Technical Specification 6.9.1.7 the following information is provided:
- a. The scope of inspections performed on each SG For all three steam generators: Full length bobbin probe inspections of all tubes. Top of the tubesheet array probe inspections around the periphery extending five tubes into the bundle. Array probe special interest locations including 80 tubes in each steam generator both legs at top of tubesheet to flow distribution baffle for the chemistry excursion.
- b. Degradation mechanisms found Degradation found included tube support plate (TSP) wear.
- c. Non-destructive examination techniques utilized for each degradation mechanism The Non-destructive examination techniques utilized bobbin coil and array probes for the detection of wear. The array probe was utilized to characterize wear indications.
- d. Location, orientation (if linear), and measured sizes (if available) of service induced indications The complete listing for service-induced indications is attached.
Tubes with tube support plate wear SG 1A - 4 tubes/6 indications SG 1B - 4 tubes/4 indication SG 1C - 4 tubes/4 indication Total - 12 tubes/14 indications No other indications of wear were reported
- e. Number of tubes plugged during the inspection outage for each active degradation mechanism No tubes were plugged.
- f. The total number and percentage of tubes plugged to date Steam Generator* 1A 1B 1C Total Plugs present prior to RFO122 5 4 3 12 Plugs added in RFO122 0 0 0 0 Total Plugs 5 4 3 12
% Plugged 0.08 0.06 0.05 0.06
- There are 6307 tubes per generator.
- g. The results of condition monitoring, including the results of tube pulls and in-situ pressure testing.
The cumulative EFPY for RFO119 was 12.22, RFO120 was 13.61, RFO121 was 15.0 and RFO122 was 16.39.
As of RFO122, the Harris Unit 1 steam generators had operated 15.11 EFPY since the first in-service inspection after replacement. In total, the Harris Unit 1 steam generators had operated 16.39 EFPY since replacement.
Condition monitoring was met for the tube to support plate degradation. All structural performance criteria were met with more than adequate margin projected through the next planned inspection at RFO125. The tube to support plate degradation could operate 14.5 EFPY before the structural and leakage criterion would be violated.
No degradation was detected in the plug visual or bowl cladding inspections.
No in-situ tests or tube pulls were performed.
FOSAR was performed at the top of tubesheet in all three steam generators. Three foreign objects were found in SG 1A. Two were legacy parts that were re-confirmed to be in their previously observed locations. The other part was a small piece of stellite material that was removed from the steam generator. One object was found in SG 1B. This part is acceptable for another three cycles of operation based on a wear evaluation. No metallic objects were found in SG 1C. The steam generators could operate no more than five cycles (7.5 effective full power years) between inspections for foreign objects and associated wear.
Sludge lancing was performed in all three steam generators. A total of fifty-eight (58) pounds of sludge were removed from all three steam generators. Thirteen (13) pounds of sludge was removed from the SG 1A. Ten (10) pounds of sludge was removed from SG 1B. Thirty-five (35) pounds of sludge was removed from SG 1C.
SG - A Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO22 CQL 20191001 01/09/2020 16:40:23
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 UTIL1 UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L IDX UTIL3l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l 3 12 .27 136 PCT 12 P5 06C .32 WAR 09H TEC .560 ZBAHS 37 C 7 l l l l 3 30 .22 116 PCT 10 P5 07C .42 WAR 09H TEC .560 ZBAHS 37 C 6 l l l l 107 78 .40 148 PCT 17 P5 07C .36 WAR 09C TEC .560 ZBAHS 37 C 8 l l l l 58 131 .40 98 PCT 17 P5 05C -.50 WAR 09C TEC .560 ZBAHS 37 C 9 l l 58 131 .31 140 PCT 14 P5 05C .38 WAR 09C TEC .560 ZBAHS 37 C 9 l l 58 131 .30 110 PCT 14 P5 04C .40 WAR 09C TEC .560 ZBAHS 37 C 9 l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 UTIL1 UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L IDX UTIL3l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
Tubes: 4 Records: 6 1 ST Max
SG - B Attachment 1 - Service Induced Degradation Shearon Harris 1 H1R22 CQL 20191001 01/09/2020 16:40:23
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 UTIL1 UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L IDX UTIL3l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l 2 1 .30 142 PCT 21 P5 06C .35 WAR 09C TEC .560 ZBAUC 21 C 10 l l l l 1 58 .12 131 PCT 11 P5 04C .41 WAR 09C TEC .560 ZBAUC 21 C 12 l l l l 58 131 .25 112 PCT 15 P5 05C .47 WAR TEC TEH .560 ZBAHS 21 H 10 l l l l 49 134 .19 87 PCT 12 P5 05C .49 WAR TEC TEH .560 ZBAHS 21 H 11 l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 UTIL1 UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L IDX UTIL3l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
Tubes: 4 Records: 4 1 ST Max
SG - C Attachment 1 - Service Induced Degradation Shearon Harris 1 H1R22 CQL 20191001 01/09/2020 16:40:23
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 UTIL1 UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L IDX UTIL3l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l 2 1 .27 94 PCT 13 P5 04C .34 WAR 09C TEC .560 ZBAHS 31 C 7 l l l l 1 86 .32 143 PCT 15 P5 05C .00 WAR 09C TEC .560 ZBAHS 31 C 8 l l l l 6 107 .20 120 PCT 10 P5 06C .38 WAR 09C TEC .560 ZBAHS 31 C 9 l l l l 1 138 .33 132 PCT 18 P5 08H .35 WAR 09H TEH .560 ZBAHS 20 H 7 l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 UTIL1 UTIL2 CRLEN CEG CRWID BEGT ENDT PDIA PTYPE CAL L IDX UTIL3l
+----+----+---------+----+----+----+-----+----+---------+---------+---------+---------+-------+----+-------+----+----+------+------+------+--+-----+---------+
Tubes: 4 Records: 4 1 ST Max