Letter Sequence Request |
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EPID:L-2018-LLL-0024, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date (Open) |
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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] |
Text
Bentley K. Jones DUKE
(__
Director, Organizational Effectiveness ENERGY Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 919.362.2305 10 CFR 50.4 September 17, 2018 Serial: HNP-18-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63
Subject:
Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date Ladies and Gentlemen:
In accordance with 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements,"Section IV.A, Duke Energy Progress, LLC (Duke Energy), is submitting this letter for approval of the extension request for the submission date of the Shearon Harris Nuclear Power Plant, Unit 1 (HNP), reactor vessel material surveillance program Capsule Z technical report.
Duke Energy withdrew the HNP reactor vessel surveillance Capsule Z on April 19, 2018. A change in the shipping container for Capsule Z identified earlier this year from a Type A cask to a Type B cask, combined with unforeseen resource restraints, has delayed the scheduled shipment of the capsule to the vendor laboratory for testing and analysis. Therefore, Duke Energy is requesting approval for the extension of the technical report submission date from April 19, 2019, to November 19, 2019.
The delay in the submittal of this technical report does not pose a significant safety impact on plant operation. The current heatup/cooldown curves (i.e., pressure/temperature limits) have a service period of 36 effective full power years (EFPY). As the HNP reactor vessel has experienced a fluence of approximately 27 EFPY, there is sufficient margin to support this proposed extension.
Please refer any questions regarding this submittal to Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.
Sincerely, cc: J. Zeiler, NRC Sr. Resident Inspector, HNP M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II
Bentley K. Jones Director, Organizational Effectiveness Harris Nuclear Plant 5413 Shearon Harris Rd New Hill, NC 27562-9300 919.362.2305 10 CFR 50.4 Serial: HNP-18-050 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63
Subject:
Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date Ladies and Gentlemen:
In accordance with 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements,"Section IV.A, Duke Energy Progress, LLC (Duke Energy), is submitting this letter for approval of the extension request for the submission date of the Shearon Harris Nuclear Power Plant, Unit 1 (HNP), reactor vessel material surveillance program Capsule Z technical report.
Duke Energy withdrew the HNP reactor vessel surveillance Capsule Z on April 19, 2018. A change in the shipping container for Capsule Z identified earlier this year from a Type A cask to a Type B cask, combined with unforeseen resource restraints, has delayed the scheduled shipment of the capsule to the vendor laboratory for testing and analysis. Therefore, Duke Energy is requesting approval for the extension of the technical report submission date from April 19, 2019, to November 19, 2019.
The delay in the submittal of this technical report does not pose a significant safety impact on plant operation. The current heatup/cooldown curves (i.e., pressure/temperature limits) have a service period of 36 effective full power years (EFPY). As the HNP reactor vessel has experienced a fluence of approximately 27 EFPY, there is sufficient margin to support this proposed extension.
Please refer any questions regarding this submittal to Jeff Robertson, Manager - Regulatory Affairs, at (919) 362-3137.
Sincerely, Bentley K. Jones cc: J. Zeiler, NRC Sr. Resident Inspector, HNP M. Barillas, NRC Project Manager, HNP NRC Regional Administrator, Region II
