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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:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements 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-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
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Text
Progress Energy. Serial: HNP-11-045 10 CFR 50.4
.MAY 5 2011 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT Ladies and Gentlemen:
In accordance with the Harris Nuclear Plant (HNP) Technical Specifications (TS), Carolina Power and Light Company (CP&L), doing business as Progress Energy Carolinas, Inc.
(PEC), submits the attached 180-Day Steam Generator Tube 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 inspection results for HNP's refueling outage number 16 (RFO- 16).
This document contains no new regulatory commitments.
Please refer any question regarding this submittal to me at (919) 362-3137.
Sincerely, Dave Corlett Supervisor - Licensing/Regulatory Programs Harris Nuclear Plant DHC/kab Enclosure cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II Mrs. B. L. Mozafari, NRC Project Manager, HNP Progress Energy Carolinas, Inc.
Harris Nuclear Plant P. 0. Box 165 New Hill, NC 27562 ~~DI
Enclosure to SERIAL: HNP- 11-045 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT FOR RFO-16 Harris Nuclear Plant, Unit I (HNP) performed steam generator (SG) inspections for all three SGs during fall 2010 refueling outage 16 (RFO-16). HNP Technical Specification (TS) 6.9.1.7, Steam Generator Tube Inspection Report, requires Carolina Power and Light Company, (CP&L), doing business at Progress Energy Carolina, Inc.(PEC), to submit a report within 180 days after the initial entry into hot shutdown (MODE 4) following completion of an inspection performed in accordance with the HNP SG Program. The report shall include:
A. The scope of inspections performed on each SG B. Active degradation mechanisms found C. Nondestructive examination (NDE) techniques utilized for each degradation mechanism D. Location, orientation (if linear), and measured sizes (if available) of service induced indications E. Number of tubes plugged during the inspection outage for each active degradation mechanism F. Total number and percentage of tubes plugged to date, and G. The results of condition, monitoring, including the results of tube pulls and in-situ testing Initial entry into hot shutdown was on November 8, 2010; therefore, this report is to be submitted by May 7, 2011.
HNP SG Design HNP is a three-loop plant where Delta 75 replacement steam generators (RSGs) were installed during the fall 2001 refueling outage 10. The Delta 75 RSGs each have 6307 thermally treated Alloy 690 U-tubes. Each U-tube has a 0.688-inch nominal outside diameter (OD), a 0.040-inch nominal wall thickness and a straight length ranging from 376.69 inches (Row 1) to 382.19 inches (Row 115). The tubes are arranged in a triangular pitch of 0.980 inches in 115 rows (parallel to the tube lane) and 141 columns. The distance between adjacent rows is 0.490 inches and between adjacent columns is 0.8487 inches. The U-bend radii range from 3.25 inches (Row
- 1) to 59.11 inches (Row 115). The innermost 17 rows are stress relieved after tube bending to minimize the potential for stress corrosion cracking. The tubesheet is 23.015 inches thick, including the 0.25-inch cladding at the bottom (primary coolant side). The tubes have full depth hydraulic expansion within the tubesheet. The tubes are supported by nine tube support plates (TSP) which have trefoil broached holes and are made of stainless steel (SA-240 type 405). The flow distribution baffle (FDB) is designed to produce sweeping flow across the tubesheet by having a central flow opening that is intended to minimize sludge deposition area on the tubesheet. The tubes are supported by four sets of stainless steel (SA-479 Type 405) anti-vibration bars (AVB) in the U-bend portion of the tube bundle.
Page 1 of 7
Enclosure to SERIAL: HNP-1 1-045 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT FOR RFO-16 A. The Scope of Inspections Performed on Each SG (A, B, and C)
- 1. Primary side inspections a) NDE Base Inspection Scope The defined scope implemented in all SGs included the following:
- 25% full length eddy current bobbin probe inspection.
" In rows one to three, only the straight legs were examined by eddy current bobbin probe inspection.
" The U-bends were examined by RPC.
0 5% eddy current bobbin probe inspection targeted at historical dents.
0 20% rotating probe coil (RPC) inspection of the outer periphery tubes -
approximately 2 tubes deep and 2 tubes along the blowdown lane, both hot leg and cold leg.
- 40% RPC inspection of the row one U-bends for tubes that were not in the 20%
inspection last time.
- Special interest RPC (freespan signals without historical resolution, bobbin I-code indications).
b) NDE Expanded Inspection Scope SG-A: Secondary side visual inspection found a foreign object which was irretrievable in SG-A and led to a bounding RPC examination of the surrounding tubes. No degradation was observed on either of the tubes which the object was touching or any of the surrounding tubes. The RPC exam did not reveal the presence of the loose part indicating that it is non-conductive.
SG-B: Wear due to a foreign object in SG-B was discovered on a tube by bobbin inspection, which led to a bounding RPC examination of the surrounding tubes.
Wear was discovered on two other tubes, which led to a further bounding RPC examination. No degradation was discovered on the surrounding tubes.
Page 2 of 7
Enclosure to SERIAL: HNP-1 1-045 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT FOR RFO-16
- 2. Secondary Side Inspections a) Sludge Lancing: Sludge Lancing was performed on all three steam generators to remove debris and corrosion products. The amounts removed from SG-A, SG-B, and SG-C was 22.5 pounds, 21.0 pounds, and 27.5 pounds, respectively. The tubesheets were. left in a clean condition.
b) Loose Parts: A Foreign Object Search and Retrieval (FOSAR) of the annulus and tube lane at the top of the tubesheet region of the secondary side of the steam generator was performed for each SG following the performance of top of the tubesheet sludge lancing. Also, a partial in-bundle inspection at the top of the tubesheet was performed for every fifth tube column in SG-C along with a visual inspection for a legacy loose part in SG-A.
During the FOSAR in SG-A, a fixed foreign object was found lodged between two outer periphery tubes in the cold leg. This prompted an expansion of the visual inspection in SG-A in the quadrant where the part was found.
The visual inspection scope was expanded to an in-bundle examination in SG-B in the quadrant where the foreign object which caused wear was found.
Neither of the expanded scope additional visual inspections found additional foreign objects.
c) Wrapper Drop: Access to the tubelane without interference was verified.
d) Feed Ring and Moisture Separators: Steam drum and feed ring inspection of all three SGs and FOSAR from these areas was performed. The steam drum inspection was a visual inspection of the steam drum down to the mid deck and remote visual.
inspection of the feedwater spray nozzles, auxiliary feedwater nozzle, inside view of the sludge collector, tube bundle, anti-vibration bars, and top support plate with trefoil holes. No foreign objects or other anomalous conditions were found.
B. Active Degradation Mechanisms Found Wear indications resulting from a foreign object were detected in one steam generator, SG-B.
A total of three tubes had indications of wear. The part was removed and the tubes plugged, Page 3 of 7
Enclosure to SERIAL: HNP- 11-045 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT FOR RFO-16 so no further degradation is possible from this foreign object. There was no observed wear at anti-vibration bars (AVBs) or tube support plates (TSPs) in any of the steam generators. No corrosion related degradation was detected.
C. NDE Techniques Utilized for Each Degradation Mechanism ETSS 21998.1 was used for sizing of the freespan wear indications.
D. Location, Orientation (if linear), and Measured Sizes (if available) of Service Induced Indications The only indications found during this inspection were volumetric wear indications in three tubes in the hot leg of SG-B from a loose part. Details are below:
Table 1. SG-B Indications Maximum Axial Length Circumferential Depth (%) (in) Extent (in)
R 28 C 135 67 0.16 0-21 R 26 C 135 37 0-16 0-17 R 26 C 133 16 0-16 0-17 E. Number of Tubes Plugged During the Inspection Outage for Each Active Degradation Mechanism A total of five tubes were plugged as a result of the inspection as described below for each SG.
Steam Generator A Two tubes were stabilized and plugged, R88 C27 and R89 C28. These were stabilized and plugged by administrative decision due to the presence of a foreign object that could not be removed during FOSAR. There were no wear indications on either of the plugged tubes or any of the adjacent tubes included in the bounding RPC examination.
Steam Generator B Three tubes were plugged due to foreign object wear: R28 C135, R26 C135, and R26 C133.
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Enclosure to SERIAL: HNP- 11-045 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT FOR RFO-16 Steam Generator C No tubes were plugged in SG-C.
F. Total Number and Percentage of Tubes Plugged to Date Each steam generator has a total of 6307 u-tubes. The total numbers of plugged tubes to date for each SG are:
Steam Generator A Total number of plugged tubes - 5 (0.08%)
Steam Generator B Total number of plugged tubes -4 (0.06%)
Steam Generator C Total number of plugged tubes - 3 (0.05%)
G. The Results of Condition Monitoring, Including the Results of Tube Pulls and In-Situ Testing There were three indications of loose parts wear, all in SG-B (see table 1 above). The maximum depth of the wear indication was 67% through-wall.
The depth sizing was performed using EPRI Examination Technique Specification Sheet (ETSS) 21998.1. This is appropriate for indications that do not have large extents in the axial or circumferential direction. The measurements using ETSS 21998.1 are reported directly and do not include the correlation between actual size and NDE measurement. The correlational and the NDE uncertainty are included in the condition monitoring limit curve.
The measured values using ETSS 21998.1 are the recorded depths. As seen in Figure 1 below (from the Degradation Assessment), the threshold for proof testing for a flaw with an axial length of 0.3 inch is 53% average depth by +Point TM Probe. The second and third tubes in the table 1 above are well below this criterion since even the maximum depth is below the limit for average depth, and therefore meet condition monitoring. The first tube, however, has a maximum depth higher than the limit set for average depth and hence requires a more detailed analysis.
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Enclosure to SERIAL: HNP- 11-045 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT FOR RFO- 16 The maximum depth of the indication in tube R28 C135 falls above the curve (see Figure 1 below) of average depth versus axial length. The maximum depth is 67% through-wall, but the average depth computed from the depth profile is 54%. A calculation determined the condition monitoring limit to be 63.6% for a 0.16-inch long axial thinning flaw. In essence, this calculation extends the axial thinning curve of Figure 1 down to 0.16 inch axial length.
Since the average depth of this flaw (54%) is below the condition monitoring limit of 63.6%,
this indication met condition monitoring. The foreign object was removed from the SG and all three tubes with indications were plugged.
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[_ Uiflfnn Thrnnk4 -0AYx TkJ1 Figure 1. Volumetric Indications Condition Monitoring Limit (+PointTM Probe)
The maximum depths of all wear indications detected in two of the three tubes were demonstrated to be below the condition monitoring limits defined in the HNP Degradation Assessment. Condition monitoring evaluation performed for the indication in the third tube showed that its average depth also falls below the condition monitoring limit for average depth. The maximum depths of the indications were well below the threshold for leakage concern. Therefore, the condition monitoring limits are satisfied for tube integrity and leakage. No tube pulls or in-situ testing was conducted during this inspection.
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Enclosure to SERIAL: HNP- 11-045 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/RENEWED LICENSE NO. NPF-63 180-DAY STEAM GENERATOR TUBE INSPECTION REPORT FOR RFO-16 COLUMNNo. 100 SDOLLUNýXl mm~Wi soh ss COLUMiN.R ) COLUMN NO. I A
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-- . -. - TYP. r Figure 2. Tubesheet Map Page 7 of 7