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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-24-0217, End of Cycle 25 (H1 R25) Inservice Inspection Program Owners Activity Report2024-09-0909 September 2024 End of Cycle 25 (H1 R25) Inservice Inspection Program Owners Activity Report RA-24-0183, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out RA-24-0172, Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2024-07-0808 July 2024 Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-24-0154, Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-06-0707 June 2024 Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable RA-24-0110, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical.2024-05-0909 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical. 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-24-0117, Cycle 26 Core Operating Limits Report, Revision O2024-04-16016 April 2024 Cycle 26 Core Operating Limits Report, Revision O RA-24-0106, Annual Environmental (Non-Radiological) Operating Report2024-04-0909 April 2024 Annual Environmental (Non-Radiological) Operating Report RA-24-0097, Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-04-0303 April 2024 Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations 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-23-0244, Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2024-03-20020 March 2024 Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RA-24-0062, 10 CFR 50 .54(q) Evaluation2024-03-0404 March 2024 10 CFR 50 .54(q) Evaluation RA-24-0033, Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2024-02-24024 February 2024 Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals RA-23-0008, Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-02-0606 February 2024 Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations 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-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 2024-09-09
[Table view] |
Text
Bentley K. Jones DUKE Director, Nuclear Organizational Effectiveness
(_
Harris Nuclear Plant ENERGY 5413 Shearon Harris Road New Hill NC 27562-9300 JUL 3 1 2018 Serial: RA-18-0066 ATTN: Document Control Desk 10 CFR 50.55a 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:
Cycle 21 Owner's Activity Report Ladies and Gentlemen:
In accordance with 10 CFR 50.55a, Duke Energy Progress, LLC, submits the attached Owner's Activity Report for Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Cycle 21 Operations and Refueling Outage 21. The 12-month extension allowed by IWA-2430 was invoked at HNP for the third 10-year inservice inspection interval. Examinations were performed during Refueling Outage 21 to satisfy the extended third inspection interval in conjunction with the fourth 10-year inspection interval, but in no case was any examination credited for both intervals.
This report has been prepared in accordance with Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 2001 Edition with 2003 Addenda as amended by ASME Code Case N-532-4,Section XI, Division 1, for the third inspection interval, and ASME Boiler and Pressure Vessel Code, 2007 Edition with 2ooa*
Addenda as amended by ASME Code Case N-532-5,Section XI, Division 1, for the fourth inspection interval.
This letter contains no new or revised Regulatory Commitments.
Please address any comments or questions regarding this matter to Jeff Robertson, Regulatory Affairs Manager, at 919-362-3137.
Sincerely, Bentley K. Jones
Enclosure:
Cycle 21 Owner's Activity Report cc: J. Zeiler, NRC Sr. Resident Inspector, HNP M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II
Bentley K. Jones Director, Nuclear Organizational Effectiveness Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 Serial: RA-18-0066 ATTN: Document Control Desk 10 CFR 50.55a 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:
Cycle 21 Owners Activity Report Ladies and Gentlemen:
In accordance with 10 CFR 50.55a, Duke Energy Progress, LLC, submits the attached Owners Activity Report for Shearon Harris Nuclear Power Plant, Unit 1 (HNP), Cycle 21 Operations and Refueling Outage 21. The 12-month extension allowed by IWA-2430 was invoked at HNP for the third 10-year inservice inspection interval. Examinations were performed during Refueling Outage 21 to satisfy the extended third inspection interval in conjunction with the fourth 10-year inspection interval, but in no case was any examination credited for both intervals.
This report has been prepared in accordance with Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 2001 Edition with 2003 Addenda as amended by ASME Code Case N-532-4,Section XI, Division 1, for the third inspection interval, and ASME Boiler and Pressure Vessel Code, 2007 Edition with 2008 Addenda as amended by ASME Code Case N-532-5,Section XI, Division 1, for the fourth inspection interval.
This letter contains no new or revised Regulatory Commitments.
Please address any comments or questions regarding this matter to Jeff Robertson, Regulatory Affairs Manager, at 919-362-3137.
Sincerely, Bentley K. Jones
Enclosure:
Cycle 21 Owners Activity Report cc: J. Zeiler, NRC Sr. Resident Inspector, HNP M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Serial RA-18-066, Enclosure SERIAL RA-18-066 ENCLOSURE CYCLE 21 OWNERS ACTIVITY REPORT (8 PAGES PLUS COVER)
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 RENEWED LICENSE NUMBER NPF-63
CASE N-532-4 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: ---"R"-'A'--'-1=8._-0=6=6=--_ _Pla nt: -----'-H=a"-r"""ris"-'-"N=uc=l=ea=r'""'P"'"'l=an""t"'",=54-"'1=3._S=h=e=a"'-ro=n..a....a...aH=ar"""r=is-'-R=o=a=d~,~N=e'""w'"'H"'"i""ll,_
1 N"'"C=--a2=7-=5=6=2-U nit No.: _ I _ Commercial Service Date: -"'"'M~a=y~2=<<~1=9=87~_ Refueling Outage No.: ~R~F~O~-=2=1_ _ _ _ _ _ _ _ __
Current Inspection Interval: --"'"'T-"'h"'"'ir=d~ln~t=e~rv=a~I_ _ _ _ _ Current Inspection Period: _ _ _ _T-'h~i"'"'rd~P~e~r~io=d_ _ _ _ __
Edition and Addenda of Section XI Applicable to the Inspection Plans: ---=2=00=1=-=Ed=i=ti=o~n""""w"""it=h=2=0=0=3-'-A-"d=d=e""n=d=a_ _ _ _ __
Date and Revision of Inspection Plans: ~A~p=r-"'il~2=7~,=20=1=7~,~R=e~vi=si=o~n~l=l~--------------- -----
Edition and Addenda of Section XI Applicable to Repair/Replacement Activities, if Different than the Inspection Plans: N/A Code Cases Used: N-432-1, N-460, N-504-4, N-508-4, N-513-3, N-516-3, N-517-1, N-526, N-528-1, N-532-4, N-552, N-566-2, N-569-1, N-578-1, N-586-1, N-593, N-597-2, N-600, N-613-1, N-624, N-629, N-638-1, N-639, N-641, N-643-2, N-648-1, N-651, N-661-2, N-663, N-685, N-695, N-696, N-697, N-700, N-705, N-706-1, N-722-1, N-729-1, N-751 and N-770-1 Certificate of Conformance ISi Inspections I certify that (a) the statements made in this report are correct; and (b) the examinations and tests meet the Inspection Plan as 7/,o /ZQ[ /j e ASME Code, S ction XI; and the completion of RFO-21 conform to the requirements of Section XI.
Signe--VC-.L..-=t---"'£~...,,._,P,,,1=9-""-"'""'-"---Angela Staller, ISi Program Manager Date Certificate of Conformance ISi Repair/Replacement I certify that (a) the statements made in this report are correct; and (b) the repair/replacement activities and evaluations supporting th completion of RFO-21 conform to the requirements of Section XI.
Certificate of lnservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of North Carolina and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, CT have inspected the items described in this Owner's 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 National Board, State, Province, and Endorsements Date 7 /, t> /zc,e, 1
CASE N-532-4 Attachment The Shearon Harris Nuclear Power Plant, Unit 1, Third Ten-Year Interval lnservice Inspection
{ISi) Plan complies with 10CFRS0.SSa(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2001 Edition with 2003 Addenda for the third interval.
This summary report is submitted pursuant to the reporting requirements of ASME Section XI as amended by ASME Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1".
Contained within this summary report are the Owner's Activity Report, Form OAR-1, and Tables 1 and 2 of Code Case N-532-4 for Shearon Harris Nuclear Power Plant during Cycle 21 and Refueling Outage 21 {RFO-21). RFO-21 is the last of three outages of the third period in the third inspection interval and includes the Repair/Replacement activities from November 12, 2016 to April 6, 2018.
2
CASE N-532-4 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Exam Category and Item Item Description Evaluation Description Number None 3
CASE N-532-4 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Item Description Description of Work Date R/R Plan Class Completed Number 3 3SW2-1459SA-1 M, 3SW2-1459SA-1, REPAIR THROUGH WALL 3/20/2018 20206079-04 LEAK, REPLACE PIPE 4
CASE N-532-5 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: ---'-'R""'A'""'-1:.::8:....-0.:.6:..:6=------Pla nt: _ __,_H.:.:a""'rr""is._N:..:..::.uc"'"l.:cea=-:r__,P....,_la:.:n-'-'t,_.=-54""'1:.:3:...S,.,h-'-'e=a"-'ro:..:n"-'-'H=-ar:.:.r.:.::is--'-R""o""a-"'d.L.-'-'N'""e-"w'""'H"'i""'II"".Nce.C:....::2'-'7-=5-=6= Unit No.: _ I _ Commercial Service Date: _ __,M"--=-ay'""2"'1--=1=9=87'--_ Refueling Outage No.: __,R""'F--=O:...-=-2=-1-_ _ _ _ _ _ _ __
Current Inspection Interval: --~F=o=u~rt~h~ln~t=e~rv=a~I_____ Current Inspection Period: ____F~i~rs=t~P=e~ri=-od~-----
Edition and Addenda of Section XI Applicable to the Inspection Plans: ---=2=-00=-7=-=Ed:.:i=ti=o:.:.n..,_w:.:.it::.:.h:..:2:.::0:..:::0:.::8c...:.A.:.::d=d,.,,e""n-=-da=---------
Date and Revision of Inspection Plans: __,A....,_u=g=u=s=-t=-30=*--=2=0=1~7~,R-'-'e=-:v=is=io=n~0~--------------------
Edition and Addenda of Section XI Applicable to Repair/Replacement Activities, if Different than the Inspection Plans: N/A Code Cases Used: N-513-3, N-532-5. N-586-1. N-600, N-613-1. N-638-6. N-639, N-643-2. N-648-1, N-651. N-705, N-716-1.
N-722-1 N-729-4 N-735 N-747 N-765 N-770-2 Certificate of Conformance ISi Inspections I certify that (a) the statements made in this report are correct; and (b) the examinations and tests meet the Inspection Plan as required by t e ASME Code,Section XI; and the completion of RFO-21 conform to the requirements of Section XI.
Signed ~..,J.L'....,.~,11,11,,-.-..,,._.~,_q...._ _ _ Angela Staller, ISi Program Manager Date 7/Jo{21J{ 8 Certificate of Conformance ISi Repair/Replacement I certify that (a) the statements made in this report are correct; and (b) the repair/replacement activities and evaluations supporting the completion of RF0-21 conform to the requirements of Section XI.
Signed rJkge'il. c.htceM Rex Chezem, Repair/Replacement PM Date G:,/2 7/Zot 8 Certificate of lnservice Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of North Carolina and employed by The Hartford Steam Boiler Inspection and Insurance Company of Hartford, CT have inspected the items described in this Owner's 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.
- ~~~L.L!::.......A~~~- - - - - -Commissions"'g 1,010. NC l&.AL, be/..-sy,,,,,,ls: Af, JJ, I, National Board, State, Province, and Endorsements
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Date 7 (, o / ?ctR 1
CASE N-532-5 Attachment The Shearon Harris Nuclear Power Plant, Unit 1, Fourth Ten-Year Interval lnservice Inspection (ISi) Plan complies with 10CFRS0.SSa(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2007 Edition with 2008 Addenda for the fourth interval.
This summary report is 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 lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1."
Contained within this summary report are the Owner's Activity Report, Form OAR-1, and Tables 1 and 2 of Code Case N-532-5 for Shearon Harris Nuclear Power Plant during Cycle 21 and Refueling Outage 21 (RFO-21). RFO-21 is the first of two outages of the first period in the fourth inspection interval and includes the Repair/Replacement activities from April 7, 2018 to May 10, 2018.
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CASE N-532-5 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Exam Category and Item Item Description Evaluation Description Number None 3
CASE N-532-5 Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Item Description Description of Work Date R/R Plan Class Completed Number 1 lRC-EO0l:008 INSIDE TEMPER BEAD WELD REPAIR PER 4/26/2018 20165265-09 FRAMATOME TRAVELER 50-9176411-007 2 AH-3 M, 1CV-E004, REPLACE LEAKING COILS ON AH-3, 4/27/2018 20248232-01 REMOVE & RE-INSTALL PIPE SUPPORTS AS NEEDED TO ALLOW FOR COIL REPLACEMENT 3 3SC3-7SB-1 M, 3SC3-7SB-1, REPAIR 1 8 1 SCREEN WASH LINE 5/5/2018 20250921-01 NEAR lSC-30 (REPLACE 3" NPS PIPING AND REMOVE/RE- INSTALL PIPE SUPPORTS AS NEEDED) 4