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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:Licensee Response to Notice of Violation
[Table view] |
Text
George T. Hamrick kDuke Vice President W Energy Harris Nuclear Plant 5413 Shearon Harris Rd New Hill NC 27562-9300 919-362-2502 November 1, 2012 Serial: HNP-12-105 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit I Docket No. 50-400
Subject:
Reply to Notice of Violation; EA-12-132 NRC Inspection Report 05000400/2012010 Ladies and Gentlemen:
Enclosed is Carolina Power & Light Company's reply to the Notice of Violation contained in the enclosure to your letter (EA-12-132) dated October 3, 2012.
This submittal contains no new regulatory commitments.
Please refer any questions regarding this submittal to David H. Corlett, Supervisor -
Licensing/Regulatory Programs, at (919) 362-3137.
Sincerely, 1dO .-v--
GTH/mgw
Enclosure:
Reply to Notice of Violation; EA- 12-132 cc: Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. A. T. Billoch Col6n, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II arc)
Document Control Desk Enclosure to HNP-12-105 Page 1 of 3 REPLY TO NOTICE OF VIOLATION; EA-12-132 NRC INSPECTION REPORT 05000400/2012010 Reported Violation A:
10 CFR 50.54(q) requires, in part, that a licensee authorized to operate a nuclear power reactor shall follow and maintain in effect emergency plans which meet the standards of 10 CFR 50.47(b).
10 CFR 50.47(b)(8) requires that adequate emergency facilities and equipment to support the emergency response are provided and maintained.
10 CFR 50, Appendix E, Section IV.E.8 (2011 version) states, in part, that the emergency facilities shall include licensee onsite technical support center and an emergency operations facility from which effective direction can be given and effective control can be exercised during an emergency.
The Harris Nuclear Plant Emergency Plan, Section 3.1, revision 57, states in part that adequate emergency facilities, communications, and equipment to support emergency response are provided and maintained.
Contrary to the above, on several occasions between August 4, 2009, and November 9, 2011, the licensee failed to maintain adequate emergency facilities and equipment to support emergency response. Specifically, the Emergency Operations Facility (EOF) normal and emergency ventilation system was in a degraded state and/or removed from service, for extended periods of time.
This violation is associated with a White SDP finding.
Reason for the Violation:
The reason for the violation is that Harris Nuclear Plant (HNP) processes and procedures to ensure the functionality and reportability requirements for the Emergency Response Facilities did not meet the standards established for the rest of the plant.
Corrective Steps Taken and Results Achieved:
- 1. Revised procedure WCP-NGGC-0300, Work Request Initiation, Screening, Prioritization and Classification on September 10, 2012, to ensure that equipment that is important to facility readiness is assigned a priority that considers its importance. The result of this action is that EOF equipment repairs are now integrated into the site's work management system.
- 2. Issued procedure PLP-717, Equipment Important to Emergency Preparedness and ERO Response on October 11, 2012, to ensure that when equipment important to Emergency Preparedness (EP) is out of service for maintenance (planned or unplanned), or is in a
Document Control Desk Enclosure to HNP- 12-105 Page 2 of 3 degraded condition, the correct restoration priority is assigned; compensatory measures are implemented; and the equipment is promptly restored to a functional operating condition.
Corrective Steps That Will Be Taken:
To preclude further noncompliance, an action is underway to document the technical requirements and administrative controls needed for the EOF and Technical Support Center to ensure performance of design and licensing basis functions. This will include design review and documentation, procedures, and line ownership. This action is currently scheduled to be completed in December 2012.
Date When Full Compliance Will Be Achieved:
Full compliance was achieved November 9, 2011, upon completion of testing following repairs on EOF emergency ventilation isolation damper D-3. The additional actions stated above will further enhance our ability to maintain compliance.
Reported Violation B:
10 CFR 50.72(b)(3)(xiii) states that a licensee shall notify the NRC as soon as practical and in all cases within eight hours of the occurrence of any event that results in a major loss of emergency assessment capability, offsite response capability, or offsite communications capability (e.g.,
significant portion of control room indication, Emergency Notification System, or offsite notification system).
Contrary to the above, on several occasions between August 4, 2009, and November 9, 2011, the licensee failed to notify the NRC within eight hours of the occurrence of a major loss of emergency assessment capability. Specifically, the licensee failed to report that the EOF normal and emergency ventilation system was in a degraded state, and/or removed from service, for extended periods of time when portions of the ventilation system were undergoing repairs, testing and maintenance, without compensatory measures.
This is a Severity Level III violation (Enforcement Policy paragraph 6.6).
Reason for the Violation:
The reason for the violation is that HNP processes and procedures to ensure the functionality and reportability requirements for the Emergency Response Facilities did not meet the standards established for the rest of the plant.
Corrective Steps Taken and Results Achieved:
- 1. Revised procedure AP-617, Reportability Determination and Notification on February 27, 2012, to specifically incorporate the reportability requirements of NUREG 1022 related to Emergency Response Facilities. As a result, HNP's reportability threshold is aligned with NRC requirements.
-0 . W Document Control Desk Enclosure to HNP-12-105 Page 3 of 3
- 2. Issued procedure PLP-717, Equipment Important to Emergency Preparedness and ERO Response on October 11, 2012, to provide guidance to the shift manager to ensure that when equipment important to EP is out of service or degraded, the condition is evaluated for reportability in accordance with procedure AP-617. The results of this action are a procedurally driven connection between equipment important to EP and reportability guidance.
Corrective Steps That Will Be Taken:
To preclude further noncompliance, an action is underway to document the technical requirements and administrative controls needed for the EOF and Technical Support Center to ensure performance of design and licensing basis functions. This will include design review and documentation, procedures, and line ownership. This action is currently scheduled to be completed in December 2012.
Date When Full Compliance Will Be Achieved:
Full compliance was achieved on October 30, 2012, when HNP submitted to the NRC Operations Center a supplement to event notification report EN-47775 for past periods where the EOF was in a non-functional status. The additional actions stated above will further enhance our ability to maintain compliance.