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Category:Inspection Report
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML22355A5062022-12-23023 December 2022 404 Cyber Notification and RFI Letter IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 IR 05000400/20210112022-01-24024 January 2022 Triennial Fire Protection Inspection Report 05000400/2021011 IR 05000400/20210102021-12-28028 December 2021 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000400/2021010 IR 05000400/20214202021-12-0707 December 2021 Security Inspection Report 05000400/2021420 IR 05000400/20210032021-11-10010 November 2021 Integrated Inspection Report 05000400/2021003 IR 05000400/20210052021-08-26026 August 2021 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2021005) IR 05000400/20210022021-08-0202 August 2021 Integrated Inspection Report 05000400/2021002 IR 05000400/20213012021-05-18018 May 2021 NRC Operator License Examination Report 05000400/2021301 IR 05000400/20210012021-04-29029 April 2021 Integrated Inspection Report 05000400/2021001 IR 05000400/20200062021-03-0303 March 2021 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2020006 IR 05000400/20200042021-01-27027 January 2021 Integrated Inspection Report 05000400/2020004 IR 05000400/20203012021-01-0808 January 2021 301 Exam Report 05000400/2020301 IR 05000335/20204012021-01-0505 January 2021 Security Baseline Inspection Report 05000335/2020401 and 05000389/2020401 IR 05000400/20200102020-12-14014 December 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000400/2020010 IR 05000400/20200112020-12-0202 December 2020 Biennial Problem Identification and Resolution Inspection Report 05000400/2020011 IR 05000400/20200032020-11-0606 November 2020 Integrated Inspection Report 05000400/2020003 IR 05000400/20204052020-11-0606 November 2020 Security Baseline Inspection Report 05000400/2020405 IR 05000400/20204032020-10-30030 October 2020 Security Baseline Inspection Report 05000400/2020403 IR 05000400/20200052020-08-24024 August 2020 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, NRC Inspection Report 05000400/2020005 IR 05000400/20200022020-08-11011 August 2020 Integrated Inspection Report 05000400/2020002 ML20223A2772020-08-10010 August 2020 Integrated Inspection Report 05000400/2020002 IR 05000400/20000092020-05-12012 May 2020 Final ASP Analysis - Shearon Harris (IR 050004002000009) IR 05000400/20200012020-05-0707 May 2020 Integrated Inspection Report 05000400/2020001 IR 05000400/20204022020-03-27027 March 2020 Security Baseline Inspection Report 05000400/2020402 IR 05000400/20190062020-03-0303 March 2020 Annual Assessment Letter for Shearon Harris Nuclear Power Plan - NRC Inspection Report 05000400/2019006 2024-01-30
[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-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating 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
[Table view] |
Text
Sean O'Connor
(_~DUKE General Manager, Nuclear Engineering ENERGYGD Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2000 October 27, 2015 Serial: HNP-15-088 ATTN: Document Control Desk 10CFR 50.4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ShearonHarris NuclearPowerPlant(HNP) Unit1 Docket No. 50-400/RenewedLicense No. NPF-63
Subject:
180-DaySteamGenerator Tube InspectionReport Ladies and Gentlemen:
In accordance with Harris Nuclear Plant (HNP) Technical Specifications (TS) Duke Energy Progrss,Inc.,submits the attached 180-Day SteamGenerator InspectionReport for HNP. This report has been prepared in accordance with TS6.9.1.7, Steam Generator Tube Inspection Report, and provides the complete results of HNP's RefuelingOutage No. 19.
This letter contains no new regulatory commitments.
Please address any comments or questions regarding this matter to John Caves at 919-362-2406 Sincerely, SeanO'Connor
Enclosure:
180-Day SteamGenerator Tube InspectionReport cc: Mr. J. D. Austin, NRG Sr. Resident Inspector, HNP Ms. M. Barillas, NRG ProjectManager, HNP Mr. V. M. Mccree, NRG RegionalAdministrator, Region II
HNP-15-088 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 (5 pages including cover)
Harris Nuclear Plant HNP1 RFO119 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.
- 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 - 0 tubes /0 indications SG 1B - 1 tube /1 indication SG 1C -1 tube/1 indication Total - 2 tubes/2 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* A B C Total Plugs present prior to 5 4 3 12 RFO119 Plugs added in RFO119 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 RFO116 was 8.16, RFO117 was 9.59, RFO118 was 10.95 and RFO119 was 12.22.
As of RFO119, the Harris Unit 1 steam generators had operated 10.94 EFPY since the first in-service inspection after replacement. In total, the Harris Unit 1 steam generators had operated 12.22 EFPY since replacement.
Condition monitoring was met for the tube support plate degradation. All structural performance criteria were met with more than adequate margin projected through the next planned inspection at RFO122.
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. No new foreign objects were discovered. Two legacy parts were confirmed in the same location as the last inspection. They were evaluated and left in service.
Sludge lancing was performed in all three steam generators. A total of sixty -five (65) pounds of sludge was removed from all three steam generators. Twenty two (22) pounds of sludge was removed from the SG A. Eighteen (18) pounds of sludge was removed from SG B . Twenty-five (25) pounds of sludge was removed from SG C.
A steam drum, sludge collector and top of the tube bundle visual inspection was performed in SG B, no degradation was detected.
SG - B Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:30:39
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l 58 131 .10 143 PCT 12 P5 05C .59 TEC TEH .560 NBAUC 5 H 13 WAR l l 58 131 .30 131 PCT 11 P33 05C .40 05C 05C .560 ZYAXP 54 C 7 WAR l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
Tubes: 1 Records: 2 1 ST Max
SG - C Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:35:12
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l 1 138 .28 133 PCT 17 P5 08H .39 09H TEH .560 NBAUL 7 H 8 WAR l l 1 138 .39 84 PCT 12 P18 08H .80 08H 08H .560 ZYAXP 12 H 7 WAR l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
Tubes: 1 Records: 2 1 ST Max
Sean O'Connor
(_~DUKE General Manager, Nuclear Engineering ENERGYGD Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2000 October 27, 2015 Serial: HNP-15-088 ATTN: Document Control Desk 10CFR 50.4 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ShearonHarris NuclearPowerPlant(HNP) Unit1 Docket No. 50-400/RenewedLicense No. NPF-63
Subject:
180-DaySteamGenerator Tube InspectionReport Ladies and Gentlemen:
In accordance with Harris Nuclear Plant (HNP) Technical Specifications (TS) Duke Energy Progrss,Inc.,submits the attached 180-Day SteamGenerator InspectionReport for HNP. This report has been prepared in accordance with TS6.9.1.7, Steam Generator Tube Inspection Report, and provides the complete results of HNP's RefuelingOutage No. 19.
This letter contains no new regulatory commitments.
Please address any comments or questions regarding this matter to John Caves at 919-362-2406 Sincerely, SeanO'Connor
Enclosure:
180-Day SteamGenerator Tube InspectionReport cc: Mr. J. D. Austin, NRG Sr. Resident Inspector, HNP Ms. M. Barillas, NRG ProjectManager, HNP Mr. V. M. Mccree, NRG RegionalAdministrator, Region II
HNP-15-088 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 (5 pages including cover)
Harris Nuclear Plant HNP1 RFO119 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.
- 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 - 0 tubes /0 indications SG 1B - 1 tube /1 indication SG 1C -1 tube/1 indication Total - 2 tubes/2 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* A B C Total Plugs present prior to 5 4 3 12 RFO119 Plugs added in RFO119 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 RFO116 was 8.16, RFO117 was 9.59, RFO118 was 10.95 and RFO119 was 12.22.
As of RFO119, the Harris Unit 1 steam generators had operated 10.94 EFPY since the first in-service inspection after replacement. In total, the Harris Unit 1 steam generators had operated 12.22 EFPY since replacement.
Condition monitoring was met for the tube support plate degradation. All structural performance criteria were met with more than adequate margin projected through the next planned inspection at RFO122.
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. No new foreign objects were discovered. Two legacy parts were confirmed in the same location as the last inspection. They were evaluated and left in service.
Sludge lancing was performed in all three steam generators. A total of sixty -five (65) pounds of sludge was removed from all three steam generators. Twenty two (22) pounds of sludge was removed from the SG A. Eighteen (18) pounds of sludge was removed from SG B . Twenty-five (25) pounds of sludge was removed from SG C.
A steam drum, sludge collector and top of the tube bundle visual inspection was performed in SG B, no degradation was detected.
SG - B Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:30:39
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l 58 131 .10 143 PCT 12 P5 05C .59 TEC TEH .560 NBAUC 5 H 13 WAR l l 58 131 .30 131 PCT 11 P33 05C .40 05C 05C .560 ZYAXP 54 C 7 WAR l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
Tubes: 1 Records: 2 1 ST Max
SG - C Attachment 1 - Service Induced Degradation Shearon Harris 1 RFO19 CQL 20150401 07/29/2015 13:35:12
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l 1 138 .28 133 PCT 17 P5 08H .39 09H TEH .560 NBAUL 7 H 8 WAR l l 1 138 .39 84 PCT 12 P18 08H .80 08H 08H .560 ZYAXP 12 H 7 WAR l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
l ROW COL VOLTS DEG IND PER CHN LOCN INCH1 INCH2 BEGT ENDT PDIA PTYPE CAL L IDX UTIL1 UTIL2l
+----+----+---------+----+----+----+----+----+---------+---------+----+----+------+------+------+--+----+--------+--------+
Tubes: 1 Records: 2 1 ST Max