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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
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Text
Ernest J. Kapopoulos, Jr.
( -, DUKE Vice President Harris Nuclear Plant ENERGY 5413 Shearon Harris Road New Hili NC 27562-9300 February 3, 2014 919 .362 .2000 Serial: HNP-14-018 ATTN: Document Control Desk 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission Washington , DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400
Subject:
Response to Request for Additional Information Regarding Response to Bulletin 2012-01 , Design Vulnerability in Electric Power System
Reference:
NRC Letter dated December 20, 2013, Request for Additional Information Regarding Response to Bulletin 2012-01 , Design Vulnerability in Electric Power System Ladies and Gentlemen:
On July 27, 2012, the Nuclear Regulatory Commission issued Bulletin 2012-01 , Design Vulnerability in Electric Power System. Carolina Power & Light Company (now Duke Energy Progress, Inc.) provided its response to Bulletin 2012-01 in a letter dated October 25, 2012. On December 20, 2013, the NRC issued the referenced request asking licensees to verify that they have completed interim corrective actions and compensatory measures and to determine the status of long-term corrective actions. The enclosure to this letter provides the response to the referenced request for the Harris Nuclear Plant.
This letter contains no new or revised Regulatory Commitments.
Please address any comments or questions regarding this matter to David Corlett, Regulatory Affairs Manager, at 919-362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 3, 2014.
Sincerely, Enclosure cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, Ill , Section Chief, N.C . DHSR (email)
Mr. A. Hon , NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
HNP-14-018 Page 1 of 2 Enclosure Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 Response to Request for Additional Information Regarding Response to Bulletin 2012-01, Design Vulnerability in Electric Power System NRC letter (ADAMS ML13351A314) dated December 20, 2013 stated:
In order for the NRC staff to complete its review of responses to the bulletin, the following additional information is requested:
- 1. Provide a summary of all interim corrective actions that have been taken since the January 30, 2012, event at Byron Station, Unit 2, to ensure that plant operators can promptly diagnose and respond to open phase conditions on the offsite power circuits for Class-1E vital buses until permanent corrective actions are completed.
- 2. Provide a status and schedule for completion of plant design changes and modifications to resolve issues with an open phase of electric power.
Response 1 - Summary of All Interim Corrective Actions Lessons learned from the events at Byron station were reviewed and various interim corrective actions were implemented based on the Harris Nuclear Plant configuration and transformer design. Based on lessons learned, the following actions were taken to ensure plant operators can promptly diagnose and respond to an open phase condition:
- The bus transfer procedure was revised to ensure three phase voltages are checked prior to bus transfers and after bus transfers are complete.
- Quarterly infrared inspections of yard equipment were completed as part of routine inspections.
- The weekly offsite power verification procedure was revised to include visual verification of offsite power connection points to ensure no visible damage.
- Turbine building auxiliary operator rounds were performed weekly which included visual checks of offsite power connections to Start-Up Transformers (SUTs). Guidance was provided on actions required if degradation of offsite power is suspected.
- Outside auxiliary operator rounds were performed daily which included guidance to perform visual checks of connection points on lines feeding the SUTs. Guidance was provided on actions if degradation of offsite power is suspected.
- Operations training was provided to describe the purpose of the visual inspections and provide guidance on the expectations of the inspections.
HNP-14-018 Page 2 of 2 Enclosure Response 2 - Status and Schedule for Completion of Plant Design Changes The Duke Energy fleet is investigating options being researched by several vendors (PSC2000, EPRI, Schweitzer, etc.) to detect open phase fault conditions. There is currently no industry technology that has been proven to detect all the required open phase fault conditions for all plant and transformer designs. With the goal of ensuring accurate detection without compromising nuclear safety or increasing plant risk, it is paramount that this new technology being evaluated be fully tested and analyzed before installation.
Design studies of the single open phase fault conditions have been started for the Duke Energy nuclear fleet. The Duke Energy nuclear fleet is fully engaged in the development of the NEI Open Phase Condition Industry Guidance Document, as well as development of enhancements to the ETAP software tool being used to analyze open phase fault conditions.
Harris Nuclear Plant intends to follow the schedule provided in the NEI industry initiative document. A provision in the schedule has already been identified for any deviations required for items such as the accommodation of outage schedules or technology availability and will be documented through the NEI exemption process.
Text
Ernest J. Kapopoulos, Jr.
( -, DUKE Vice President Harris Nuclear Plant ENERGY 5413 Shearon Harris Road New Hili NC 27562-9300 February 3, 2014 919 .362 .2000 Serial: HNP-14-018 ATTN: Document Control Desk 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission Washington , DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400
Subject:
Response to Request for Additional Information Regarding Response to Bulletin 2012-01 , Design Vulnerability in Electric Power System
Reference:
NRC Letter dated December 20, 2013, Request for Additional Information Regarding Response to Bulletin 2012-01 , Design Vulnerability in Electric Power System Ladies and Gentlemen:
On July 27, 2012, the Nuclear Regulatory Commission issued Bulletin 2012-01 , Design Vulnerability in Electric Power System. Carolina Power & Light Company (now Duke Energy Progress, Inc.) provided its response to Bulletin 2012-01 in a letter dated October 25, 2012. On December 20, 2013, the NRC issued the referenced request asking licensees to verify that they have completed interim corrective actions and compensatory measures and to determine the status of long-term corrective actions. The enclosure to this letter provides the response to the referenced request for the Harris Nuclear Plant.
This letter contains no new or revised Regulatory Commitments.
Please address any comments or questions regarding this matter to David Corlett, Regulatory Affairs Manager, at 919-362-3137.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 3, 2014.
Sincerely, Enclosure cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Mr. W. L. Cox, Ill , Section Chief, N.C . DHSR (email)
Mr. A. Hon , NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
HNP-14-018 Page 1 of 2 Enclosure Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 Response to Request for Additional Information Regarding Response to Bulletin 2012-01, Design Vulnerability in Electric Power System NRC letter (ADAMS ML13351A314) dated December 20, 2013 stated:
In order for the NRC staff to complete its review of responses to the bulletin, the following additional information is requested:
- 1. Provide a summary of all interim corrective actions that have been taken since the January 30, 2012, event at Byron Station, Unit 2, to ensure that plant operators can promptly diagnose and respond to open phase conditions on the offsite power circuits for Class-1E vital buses until permanent corrective actions are completed.
- 2. Provide a status and schedule for completion of plant design changes and modifications to resolve issues with an open phase of electric power.
Response 1 - Summary of All Interim Corrective Actions Lessons learned from the events at Byron station were reviewed and various interim corrective actions were implemented based on the Harris Nuclear Plant configuration and transformer design. Based on lessons learned, the following actions were taken to ensure plant operators can promptly diagnose and respond to an open phase condition:
- The bus transfer procedure was revised to ensure three phase voltages are checked prior to bus transfers and after bus transfers are complete.
- Quarterly infrared inspections of yard equipment were completed as part of routine inspections.
- The weekly offsite power verification procedure was revised to include visual verification of offsite power connection points to ensure no visible damage.
- Turbine building auxiliary operator rounds were performed weekly which included visual checks of offsite power connections to Start-Up Transformers (SUTs). Guidance was provided on actions required if degradation of offsite power is suspected.
- Outside auxiliary operator rounds were performed daily which included guidance to perform visual checks of connection points on lines feeding the SUTs. Guidance was provided on actions if degradation of offsite power is suspected.
- Operations training was provided to describe the purpose of the visual inspections and provide guidance on the expectations of the inspections.
HNP-14-018 Page 2 of 2 Enclosure Response 2 - Status and Schedule for Completion of Plant Design Changes The Duke Energy fleet is investigating options being researched by several vendors (PSC2000, EPRI, Schweitzer, etc.) to detect open phase fault conditions. There is currently no industry technology that has been proven to detect all the required open phase fault conditions for all plant and transformer designs. With the goal of ensuring accurate detection without compromising nuclear safety or increasing plant risk, it is paramount that this new technology being evaluated be fully tested and analyzed before installation.
Design studies of the single open phase fault conditions have been started for the Duke Energy nuclear fleet. The Duke Energy nuclear fleet is fully engaged in the development of the NEI Open Phase Condition Industry Guidance Document, as well as development of enhancements to the ETAP software tool being used to analyze open phase fault conditions.
Harris Nuclear Plant intends to follow the schedule provided in the NEI industry initiative document. A provision in the schedule has already been identified for any deviations required for items such as the accommodation of outage schedules or technology availability and will be documented through the NEI exemption process.