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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
Bentley K. Jones Director, Organizational Effectiveness Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 10 CFR 50.90 September 14, 2017 Serial: HNP-17-073 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:
Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses Ladies and Gentlemen:
By letter dated June 28, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17193B165), Duke Energy Progress, LLC (Duke Energy),
requested an amendment to the Technical Specifications (TSs) of Renewed Facility Operating License No. NPF-63 for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed license amendment would revise the TS for fuel storage criticality to account for the use of Metamic neutron absorbing spent fuel pool rack inserts and soluble boron for the purpose of criticality control in the Boiling Water Reactor (BWR) storage racks that currently credit Boraflex.
The Nuclear Regulatory Commission (NRC) staff has reviewed the application and concluded that the information delineated in the enclosure to their letter dated August 30, 2017 (ADAMS Accession No. ML17241A018), is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. In response to the request for supplemental information, HNP is submitting the enclosed additional information to support acceptance review of the proposed amendment.
The content of this supplemental correspondence does not change the No Significant Hazards Consideration provided in the original submittal.
No regulatory commitments are contained in this letter.
In accordance with 10 CFR 50.91(b), HNP is providing the state of North Carolina with a copy of this supplemental correspondence.
Should you have any questions regarding this submittal, please contact Jeffery Robertson, HNP Regulatory Affairs Manager, at (919) 362-3137.
U.S. Nuclear Regulatory Commission Page 2 Serial: HNP-17-073 I declare under penalty of perjury that the foregoing is true and correct.
Executed on September 14, 2017.
Sincerely, Bentley K. Jones cc: J. Zeiler, NRC Sr. Resident Inspector, HNP W. L. Cox, III, Section Chief N.C. DHSR M. Barillas, NRC Project Manager, HNP C. Haney, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Serial: HNP-17-073 Enclosure HNP-17-073 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 SUPPLEMENTAL INFORMATION FOR LICENSE AMENDMENT REQUEST REGARDING SPENT FUEL STORAGE POOL CRITICALITY ANALYSES Enclosure (3 pages including cover)
U.S. Nuclear Regulatory Commission Page 2 of 3 Serial: HNP-17-073 Enclosure
1.0 INTRODUCTION
By letter dated June 28, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17193B165), Duke Energy Progress, LLC (Duke Energy),
requested an amendment to the Technical Specifications (TSs) of Renewed Facility Operating License No. NPF-63 for Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed license amendment would revise the TS for fuel storage criticality to account for the use of Metamic neutron absorbing spent fuel pool rack inserts and soluble boron for the purpose of criticality control in the Boiling Water Reactor (BWR) storage racks that currently credit Boraflex.
During the Nuclear Regulatory Commission (NRC) staffs acceptance review of the requested license amendment, the NRC staff found the application contained an insufficiency related to the description of the applicable regulatory requirements for the proposed changes. As such, supplemental information has been requested to enable the NRC staff to begin its detailed review. Duke Energys response is provided herein with the requested information discussing how the applicable regulatory requirements will continue to be met.
2.0 INSUFFICIENCY Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.90, Application for amendment of license, construction permit, or early site permit, states that license amendment requests (LARs) fully describe the changes desired. Section 50.36 of 10 CFR is the governing regulation for TSs and contains the regulatory requirements for TS categories, including: Safety Limits, Limiting Conditions for Operation, Surveillance Requirements, Design Features, and Administrative Controls.
Section 4.0 of the LAR contains discussions regarding whether or not the regulatory requirements of 10 CFR 50.68, 10 CFR Part 50 Appendix A, General Design Criterion (GDC) 61 and GDC 62 would continue to be met. However, Section 4.0 contains no discussion of whether or not the regulatory requirements of 10 CFR 50.36 will continue to be met, given the proposed changes to TSs. As such, it has been requested that the LAR be supplemented by providing a full description of the applicable regulatory requirements for the proposed changes, including 10 CFR 50.36, and describe how these requirements will continue to be met.
3.0 DUKE ENERGY RESPONSE 10 CFR 50.36, Technical Specifications, paragraph (c)(4), Design Features, states that design features to be included are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered by the other TS categories (i.e., Safety Limits, Limiting Conditions for Operation, Surveillance Requirements). The LAR requests changes to TS 5.6.1.3, BWR Storage Racks in Pools A and B, to reflect the respective design features of the two BWR rack types utilized in these pools, including adjusted requirements for the racks that will credit the use of neutron absorbing Metamic inserts and soluble boron for criticality control in place of the existing credited Boraflex. The incorporation of these adjusted requirements for the BWR storage racks in Pools A and B and the addition of the new figures to address the orientation
U.S. Nuclear Regulatory Commission Page 3 of 3 Serial: HNP-17-073 Enclosure of the rack inserts in the pools will ensure that the HNP fuel storage design features remain in compliance with the requirements of 10 CFR 50.36(c)(4).
As noted above, Section 4.0 of the LAR contains discussion pertaining to the continuance in meeting the regulatory requirements of 10 CFR 50.68, and 10 CFR Part 50 Appendix A, General Design Criterion (GDC) 61 and GDC 62. Therefore, they are not included in this supplement.
