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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
[Table view] Category:Report
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-21-0097, Notification of Permit Revision Request Regarding Copper and Zinc Limits2021-03-15015 March 2021 Notification of Permit Revision Request Regarding Copper and Zinc Limits RA-20-0381, CFR 50.54( Q) Screening Evaluation Form for Revisions2020-12-0808 December 2020 CFR 50.54( Q) Screening Evaluation Form for Revisions RA-20-0335, Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in .2020-11-24024 November 2020 Response to Request for Additional Information Regarding License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in . RA-20-0032, License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits2020-03-0606 March 2020 License Amendment Request to Reduce the Minimum Required Reactor Coolant System Flow Rate and Update the List of Analytical Methods Used in the Determination of Core Operating Limits RA-19-0403, Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule Z2019-10-23023 October 2019 Submittal of the Summary Technical Report for the Reactor Pressure Vessel Surveillance Program Capsule Z RA-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 RA-18-0179, 90-Day Special Report2018-10-0404 October 2018 90-Day Special Report ML18230A7562018-08-18018 August 2018 Fault Investigation, Responses to Mr. W. R. Butler'S Letter of May 16, 1975 ML18230A7592018-08-18018 August 2018 Fault Investigation, Progress Report, Volume 1 of 2 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 RA-17-0040, Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions)2017-08-15015 August 2017 Providing Methodology Reports DPC-NE-1008-P, Revision 0, DPC-NF-2010, Revision 3, and DPC-NE-2011-P, Revision 2. (Non-Proprietary Versions) HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-006, Submittal of Cycle 20 Activity Report2017-01-30030 January 2017 Submittal of Cycle 20 Activity Report HNP-16-083, Mitigating Strategies Assessment Report for Flooding Hazard Information2016-12-21021 December 2016 Mitigating Strategies Assessment Report for Flooding Hazard Information RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P2016-10-0303 October 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P RA-16-0023, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P2016-05-0404 May 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-1008-P HNP-16-017, Transmittal of Summary of a 10 CFR 50.54(q) Evaluation2016-02-29029 February 2016 Transmittal of Summary of a 10 CFR 50.54(q) Evaluation RA-15-0042, Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis.2015-11-19019 November 2015 Application to Revise Technical Specifications to Adopt Methodology Report DPC-NE-3008-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis. ML15301A5572015-11-0202 November 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request Flood Causing Mechanisms Reevaluations RA-15-0031, Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors.2015-08-19019 August 2015 Application to Revise Technical Specifications for Methodology Report DPC-NE-1008-P, Revision 0, Nuclear Design Methodology Using CASMO-5/Simulate-3 for Westinghouse Reactors. RA-15-0022, Annual Report of Changes Pursuant to 10 CFR 50.462015-05-14014 May 2015 Annual Report of Changes Pursuant to 10 CFR 50.46 ML15126A0892015-04-30030 April 2015 EAL Bases HNP-15-027, Flood Hazard Reevaluation Report, Revision 12015-04-0101 April 2015 Flood Hazard Reevaluation Report, Revision 1 HNP-14-035, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.32014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 ML13364A2142014-02-12012 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14030A1022014-01-29029 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Shearon Harris Nuclear Power Plant, Unit 1, TAC No.: MF0874 HNP-13-083, Submittal of Summaries of 10 CFR 50.54(q) Evaluations2013-08-0101 August 2013 Submittal of Summaries of 10 CFR 50.54(q) Evaluations HNP-13-046, Report of Changes Pursuant to 10 CFR 50.592013-04-29029 April 2013 Report of Changes Pursuant to 10 CFR 50.59 ML12355A2022012-12-18018 December 2012 Evacuation Time Estimates Analysis HNP-12-119, Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12158A4522012-06-0808 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to Fukushima Daiichi Nuclear Power Plant Accident ML12067A1802012-02-29029 February 2012 ANP-3011Q1(NP), Revision 000, Harris Nuclear Plant Unit 1 Realistic Large Break LOCA Analysis. Enclosure 4 Response to Request for Additional Information (Non-Proprietary) ML1019304172010-05-0606 May 2010 Tritium Database Report ML1008904242010-03-0202 March 2010 NAI-1478-001, Revision 1, HNP CSAT Volume, Flow and Naoh Concentration Range Revisions. ML1008905932010-01-31031 January 2010 Application for Revision to Technical Specification Core Operating Limits Report References, ANP-2853(NP), Rev. 0, Realistic Large Break LOCA Summary Report. ML1002508582010-01-18018 January 2010 Holtec Report, No. HI-2043321, Rev. 6, Critically Safety Analyses of BWR Fuel Without Credit for Boraflex in the Racks at the Harris Nuclear Power Station. ML1003402842010-01-12012 January 2010 NAI-1478-001, Revision 0, HNP CSAT Volume, Flow and Naoh Concentration Range Revisions ML1020301622009-12-31031 December 2009 Cooling Tower Blowdown Line Supplemental Groundwater Assessment Report, Shearon Harris Nuclear Power Plant ML1019400962009-07-0808 July 2009 Nrc/Harris Split Sample Results ML0921500542009-05-31031 May 2009 ANP-2693(NP), Revision 0, Loss of Forced Reactor Coolant Flow Analysis for Harris Nuclear Plant, Unit 1, Enclosure 4 to Serial: HNP-09-068 HNP-09-056, Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2009-05-22022 May 2009 Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) ML1020301602009-04-30030 April 2009 Cooling Tower Blowdown Line Assessment Report, Shearon Harris Nuclear Power Plant ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 HNP-08-015, Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors2008-02-28028 February 2008 Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors HNP-07-178, Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition2008-01-10010 January 2008 Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML0800705312008-01-0909 January 2008 Review of the Fire Probabilistic Risk Assessment Model to Support Implementation of National Fire Protection Association (NFPA) Standard NFPA-805 ML0724202552007-08-30030 August 2007 NRC Allegation Report RII-2005-A-0165 ML0719801952007-07-30030 July 2007 Environmental Impact Statement Scoping Process Summary Report Shearon Harris Nuclear Power Plant - July 2007 ML0720502142007-07-19019 July 2007 Afpb Staff Response to NFPA 805 Transition Pilot Plant FAQ 06-0008, Revision 5 2024-09-09
[Table view] Category:Miscellaneous
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-19-0223, Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.462019-05-30030 May 2019 Annual Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models Pursuant to 10CFR 50.46 ML18230A7562018-08-18018 August 2018 Fault Investigation, Responses to Mr. W. R. Butler'S Letter of May 16, 1975 ML18230A7592018-08-18018 August 2018 Fault Investigation, Progress Report, Volume 1 of 2 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-17-006, Submittal of Cycle 20 Activity Report2017-01-30030 January 2017 Submittal of Cycle 20 Activity Report HNP-16-083, Mitigating Strategies Assessment Report for Flooding Hazard Information2016-12-21021 December 2016 Mitigating Strategies Assessment Report for Flooding Hazard Information RA-16-0024, Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P2016-10-0303 October 2016 Supplemental Information for License Amendment Request Regarding Methodology Report DPC-NE-3008-P HNP-16-017, Transmittal of Summary of a 10 CFR 50.54(q) Evaluation2016-02-29029 February 2016 Transmittal of Summary of a 10 CFR 50.54(q) Evaluation ML15301A5572015-11-0202 November 2015 Supplement to Staff Assessment of Response to 10 CFR 50.54(f) Information Request Flood Causing Mechanisms Reevaluations RA-15-0022, Annual Report of Changes Pursuant to 10 CFR 50.462015-05-14014 May 2015 Annual Report of Changes Pursuant to 10 CFR 50.46 ML15126A0892015-04-30030 April 2015 EAL Bases HNP-15-027, Flood Hazard Reevaluation Report, Revision 12015-04-0101 April 2015 Flood Hazard Reevaluation Report, Revision 1 HNP-14-035, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.32014-03-27027 March 2014 Seismic Hazard and Screening Report (CEUS Sites), Response to NRC 10 CFR 50.54(f) Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 HNP-13-083, Submittal of Summaries of 10 CFR 50.54(q) Evaluations2013-08-0101 August 2013 Submittal of Summaries of 10 CFR 50.54(q) Evaluations HNP-13-046, Report of Changes Pursuant to 10 CFR 50.592013-04-29029 April 2013 Report of Changes Pursuant to 10 CFR 50.59 ML12355A2022012-12-18018 December 2012 Evacuation Time Estimates Analysis HNP-12-119, Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Response to Recommendation 2.3 Seismic Walkdown of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12158A4522012-06-0808 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to Fukushima Daiichi Nuclear Power Plant Accident ML1019304172010-05-0606 May 2010 Tritium Database Report ML1020301622009-12-31031 December 2009 Cooling Tower Blowdown Line Supplemental Groundwater Assessment Report, Shearon Harris Nuclear Power Plant ML1019400962009-07-0808 July 2009 Nrc/Harris Split Sample Results HNP-09-056, Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2009-05-22022 May 2009 Non-Security Sensitive Version of Original Request for License Amendment to Adopt NFPA 805 Performance-Based Standards for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) ML1020301602009-04-30030 April 2009 Cooling Tower Blowdown Line Assessment Report, Shearon Harris Nuclear Power Plant HNP-08-015, Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors2008-02-28028 February 2008 Supplemental Response to NRC GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-water Reactors HNP-07-178, Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition2008-01-10010 January 2008 Revision 0a, Transition to 10 CFR 50.48(c) - NFPA 805 Performance- Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition ML0800705312008-01-0909 January 2008 Review of the Fire Probabilistic Risk Assessment Model to Support Implementation of National Fire Protection Association (NFPA) Standard NFPA-805 ML0724202552007-08-30030 August 2007 NRC Allegation Report RII-2005-A-0165 ML0719801952007-07-30030 July 2007 Environmental Impact Statement Scoping Process Summary Report Shearon Harris Nuclear Power Plant - July 2007 ML0720502142007-07-19019 July 2007 Afpb Staff Response to NFPA 805 Transition Pilot Plant FAQ 06-0008, Revision 5 HNP-07-068, Day Special Report of the Metal Impact Monitoring System2007-05-14014 May 2007 Day Special Report of the Metal Impact Monitoring System ML0712701832007-05-0404 May 2007 Audit and Review Plan for Plant Aging Managment Programs, Aging Management Reviews, and Time-Limited Aging Analyses for the Harris Nuclear Plant. ML0632001682006-10-30030 October 2006 G20060793 - Progress Energy Paper Anti-Nuclear Groups Files Petition to Shut Down Harris Plant HNP-06-073, Day Special Report Steam Generator Tube Plugging During RFO-132006-05-0505 May 2006 Day Special Report Steam Generator Tube Plugging During RFO-13 ML0608107112006-03-22022 March 2006 for the Record: Summary of Nrc'S Review of the Recent Security Issues at the Shearon Harris Nuclear Plant HNP-06-031, Notification of NPDES Permit Renewal Application2006-02-10010 February 2006 Notification of NPDES Permit Renewal Application ML0515204452005-05-27027 May 2005 Significant Adverse Condition Investigation Report HNP-05-067, Emergency Core Cooling System Evaluation Changes2005-05-25025 May 2005 Emergency Core Cooling System Evaluation Changes HNP-05-059, Emergency Response Data System (ERDS) Data Point Library Changes2005-05-12012 May 2005 Emergency Response Data System (ERDS) Data Point Library Changes ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement HNP-04-083, Day Special Report, Steam Generator Tube Plugging2004-05-27027 May 2004 Day Special Report, Steam Generator Tube Plugging ML0318909362003-07-10010 July 2003 Relaxation of the Order, Exercising Enforcement Discretion, and Extension of the Time to Submit an Answer or Request a Hearing Regarding Order EA-03-038, Fitness-for-Duty Enhancements for Nuclear Security Force Personnel for Brunswick, Crys 2024-09-09
[Table view] |
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Bentley K. Jones J,.., DUKE Director, Nuclear Organizational Effectiveness Harris Nuclear Plant
~ ENERGY 5413 Shearon Harris Road New Hill NC 27562-9300 January 30, 2017 Serial: HNP-17-006 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 I Renewed License No. NPF-63
Subject:
Cycle 20 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 the Shearon Harris Nuclear Power Plant, Unit 1. 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 addenda through 2003 as amended by ASME Code Case N-532-4,Section XI, Division 1. This report is for HNP's Cycle 20 Operations and Refueling Outage 20 of the third 10-year lnservice 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 20 Owner's Activity Report cc: Mr. R. Patterson, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II
Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63 Cycle 20 Owners Activity Report (4 pages plus cover)
Summary The Shearon Harris Nuclear Power Plant, Unit 1, Third Ten-Year Interval Inservice Inspection Plan complies with 10CFR50.55a(g), which implements, by reference, the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2001 Edition with 2003 Addenda.
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 Inservice Summary Report Preparation and Submission Section XI, Division 1.
Contained within this summary report are the Owners Activity Report, Form OAR-1, and Tables 1 and 2 of Code Case N-532-4 for Shearon Harris Nuclear Power Plant during Cycle 20 and Refueling Outage 20 (RFO-20). RFO-20 is the second of three outages of the third period in the third inspection interval and includes the Repair/Replacement activities from May 16, 2015, to November 11, 2016.
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FORM OAR-1 OWNER'S ACTIVITY REPORT Re po rt Number: _ __,_H"-N'-'-P--1=7'---=00=-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"--'-'H=a'-'rr=is'"'"R=o=a=d_,_,_,_N=e""w'""'H"'"i""ll',""N'-'-C=-=2:..:.7-=5=6=2-Unit No.: _ I _ Commercial Service Date: _ ....M'"""a~v~2~*~1=9=87____ Refueling Outage No.: -R~F-=0=--=20=------------
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=da=--------
Date and Revision of Inspection Plans: _N'"'"o=-v""e""m""b=e:..:.r-=30L...:2=0=16"--'-'R=ev""'is=i=o"-n-=1=0-------------------
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, 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 e ASME Code,Section XI; and the completion of RF0-20 conform to the requirements of Section XI.
Signed ..J.L_!..!.~~~""-ll.~~~~:.i._ __ Angela Staller, ISi Program Manager Date l/Z--4/l 1 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 RF0-20 conform to the requirements of Section XI.
-#~~~""""'--=r----- Adam Zimandy, Repair/Replacement PM Date 1/zrf 7 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.
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Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Exam Category and Item Item Description Evaluation Description Number Category F-A, Item F1.20 Rigid strut support FW-H-0102 The support was evaluated as (R/R Plan number 20117235-01) found with spherical bearing operable by Engineering assembly dislodged with paddle Evaluation following discovery.
against bracket The dislodged spherical bearing will be repaired during RFO-21.
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Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Class Component ID Description of Work Date R/R Plan Completed Number 1 1RC-E001:008 M,CONTINGENCY WELD REPAIRS, RV HEAD 11/2/2016 13543169-09/14 1 1RC-E001:008 NON-WELDED REPAIR OF PT INDICATION BY 11/2/2016 13543169-13 REDUCING INDICATION TO ACCEPTABLE SIZE THROUGH GRINDING ONLY, NOZZLE 23 2 BD-H-0357 M, BD-H-0357, SNUBBER NEEDS TO BE RE-SET 10/24/2016 13519471-01 DURING RFO-20 2 2SW10-37SA-1 M, THROUGH WALL LEAK ON SW FROM AH-2, 11/07/2016 20121639-01 2SW10-37SA-1 3 1AS-345 M, 1AS-345, REMOVE, INSPECT, REINSTALL; 7/18/2016 13374314-01 REPLACE BOLTING 3 1AS-344 M, 1AS-344, REMOVE, INSPECT, REINSTALL 08/01/2016 13374315-01 3 CC-H-1446 M, CC-H-1446, SNUBBER NEEDS TO BE RE-SET 10/24/2016 13519474-01 DURING RFO-20 3 1SC-BAY6 M, 1SC-BAY6, ESW SCREEN WASH PUMP HAS 04/06/2016 20010087-01 OIL LEAK 3 1SW-130 M, EC 71134, REPLACE VALVE 1SW-130 WITH 10/27/2016 20019035-01 A SS VALVE.
3 1SW-83 M, 1SW-83, REPLACE CAP SCREWS 07/20/2016 20048488-01 3 1SW-85 M,1SW-85, REPLACE CAP SCREWS 07/21/2016 20048491-01 3 1SW-210 M, 1SW-210, REPLACE CAP SCREWS 08/09/2016 20048492-01 3 1SW-119 M, 1SW-119, REPLACE CAP SCREWS 07/21/2016 20048509-01 3 1SW-70 M, 1SW-70, REPLACE CAP SCREWS 11/10/2016 20048510-01 3 1SW-58 M, 1SW-58, REPLACE CAP SCREWS 11/7/2016 20048511-01 3 1SW-266 M, 1SW-266, REPLACE CAP SCREWS 8/9/2016 20048512-01 3 1SW-116 M, 1SW-116, REPLACE CAP SCREWS 7/21/2016 20048513-01 3 1SW-118 M, 1SW-118, REPLACE CAP SCREWS 11/7/2016 20048514-01 3 1SW-33 M, 1SW-33, REPLACE CAP SCREWS 11/7/2016 20048515-01 3 3SW1.5-167SA-1 M, 3SW1.5-167SA-1, 1 DPM THRUWALL LEAK 4/1/2016 20069074-01 AT COOLER; REPAIR LEAK 3 3SC4-8SB-1 3SC4-8SB-1, LEAK REPAIR PIPING 6/23/2016 20089243-02 REPLACEMENT 4