|
|---|
Category:Letter type:RA
MONTHYEARRA-23-0242, Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)2024-01-10010 January 2024
Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations in Accordance with 10 CFR 50.55a(z)(2)
RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024
Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX
RA-23-0295, Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval2024-01-0404 January 2024
Delay of Planned End Date for Fourth 10-Year Inservice Testing (1ST) Program Interval
RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023
Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023
RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023
Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power
RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023
Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes
RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023
Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes
RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023
Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)
RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023
Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023
Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require
RA-23-0127, 10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record2023-06-28028 June 2023
10 CFR 50.55a(g)(4)(iv) Request to Use a Subsequent Edition of ASME Section XI Referenced in 10 CFR 50.SSa(a) for ISI Code of Record
RA-23-0135, Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory2023-06-0707 June 2023
Submittal of 30 Day Report Per 10 CFR 26.719(c), Unsatisfactory Performance of Health and Human Services Certified Laboratory
RA-23-0041, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-30030 May 2023
Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
RA-23-0118, Cycle 29, Revision 1, Core Operating Limits Report (COLR)2023-05-0303 May 2023
Cycle 29, Revision 1, Core Operating Limits Report (COLR)
RA-23-0117, Report of Changes to Duke Energy McGuire Emergency Plan Annex2023-05-0101 May 2023
Report of Changes to Duke Energy McGuire Emergency Plan Annex
RA-23-0044, Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.462023-04-26026 April 2023
Aduke Energy Annual Report of Changes Pursuant to 10 CFR 50.46
RA-23-0047, Duke Energy Annual Radiological Environmental Operating Report - 20222023-04-26026 April 2023
Duke Energy Annual Radiological Environmental Operating Report - 2022
RA-23-0046, Annual Radioactive Effluent Release Report - 20222023-04-24024 April 2023
Annual Radioactive Effluent Release Report - 2022
RA-23-0037, Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis)2023-03-30030 March 2023
Duke Energy - Decommissioning Funding Plan for Independent Spent Fuel Storage Installations (Isfsis)
RA-23-0039, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2023-03-30030 March 2023
10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums
RA-23-0040, Onsite Property Insurance Coverage2023-03-30030 March 2023
Onsite Property Insurance Coverage
RA-23-0036, Biennial Decommissioning Financial Assurance Reports2023-03-30030 March 2023
Biennial Decommissioning Financial Assurance Reports
RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report2023-03-16016 March 2023
Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report
RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds2023-02-28028 February 2023
Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds
RA-23-0065, Report of Changes to McGuire EAL Technical Basis Document2023-02-23023 February 2023
Report of Changes to McGuire EAL Technical Basis Document
RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-17017 February 2023
Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023
Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023
Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements
RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023
License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)2023-02-15015 February 2023
End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)
RA-23-0001, Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI2023-02-0202 February 2023
Request to Use a Provision of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI
RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023
License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies
RA-22-0256, Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-01-23023 January 2023
Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)
RA-22-0335, Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab2022-12-0505 December 2022
Submittal of 30-Day Report Per 10CFR26.719(c)(1) - Unsatisfactory Performance of a Health & Human Services Certified Lab
RA-22-0312, Report of Changes to McGuire Emergency Plan Annex2022-10-26026 October 2022
Report of Changes to McGuire Emergency Plan Annex
RA-22-0303, End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report2022-10-25025 October 2022
End of Cycle 28 (M1 R28) Steam Generator Tube Inspection Report
RA-22-0291, Report of Changes to Emergency Plan Implementing Procedures2022-10-17017 October 2022
Report of Changes to Emergency Plan Implementing Procedures
RA-22-0024, Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components2022-09-21021 September 2022
Relief Requested in Accordance with 10 CFR 50.55a(g)(5)(iii) for Volumetric Examination of Class 1 Components
RA-22-0253, Independent Spent Fuel Storage Installation (Isfsi), Register Use of Casks2022-08-25025 August 2022
Independent Spent Fuel Storage Installation (Isfsi), Register Use of Casks
RA-22-0178, End of Cycle 28 (M1R28) Inservice Inspection Summary Report2022-08-0808 August 2022
End of Cycle 28 (M1R28) Inservice Inspection Summary Report
RA-22-0151, Duke Energy Common Emergency Plan, Revision 2, Summary of Changes2022-05-24024 May 2022
Duke Energy Common Emergency Plan, Revision 2, Summary of Changes
RA-22-0148, 10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory2022-05-16016 May 2022
10 CFR 26.719(c)(1) Report - Unsatisfactory Performance of a Health and Human Services Certified Laboratory
RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022
Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility
RA-22-0149, Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-28028 April 2022
Supplement to the Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System
RA-22-0028, Annual Report of Changes Pursuant to 10 CFR 50.462022-04-27027 April 2022
Annual Report of Changes Pursuant to 10 CFR 50.46
RA-22-0029, Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 20212022-04-27027 April 2022
Shearon Harris Power Plant, McGuire Nuclear Station, Oconee Nuclear Station, H. B. Robinson Steam Electric Plant - Annual Radioactive Effluent Release Report - 2021
RA-22-0127, Interim Part 21 Report of a Deviation or Failure to Comply for Cutler-Hammer Relay2022-04-0808 April 2022
Interim Part 21 Report of a Deviation or Failure to Comply for Cutler-Hammer Relay
RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022
Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology
RA-22-0080, Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System2022-04-0707 April 2022
Independent Spent Fuel Storage Installation, McGuire, Units 1 & 2, Independent Spent Fuel Storage Installation, Request for an Exemption to the Requirements of Certificate of Compliance No. 1031 for the NAC Magnastor Storage System
2024-01-08
[Table view]
Category:Written Event Report (30 or 60 day)
[Table view] |
Text
Brent A. Bare
£ ., DUKE Station Plant Manager McGuire Nuclear Station
~ ENERGY Duke Energy MG01VP 112700 Hagers Ferry Road Huntersville, NC 28078 o: 980 .875.4111 Brent Bare@duke-energy.com September 25, 2023 10 CFR 50.4 Serial No: RA-23-0243 U.S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington , D.C. 20555-0001
Subject:
Duke Energy Carolinas, LLC McGuire Nuclear Station Renewed Facility Operating License Nos. NPF-17 Docket No. 50-370 Special Report 370-2023-001 Pursuant to Selected Licensee Commitments (SLC) Manual Section 16.7.1, Required Action A.2 , attached is Special Report 370-2023-001 concerning an event where the Unit 2 Anticipated Transients Without Scram (ATWS) and ATWS Mitigation System Actuation Circuitry (AMSAC)
System has been nonfunctional for a period greater than 37 days. This event is of no significance with respect to the health and safety of the public.
This document contains no new regulatory commitments . Should you have any questions, please contact Jeff Thomas , McGuire Regulatory Affairs , at 980-875-4499.
Sincerely, Brent A. Bare Station Plant Manager McGuire Nuclear Station Attachment
U.S, Nuclear Regulatory Commission RA-23-0243 Page 2 cc (with Attachment):
Laura A. Dudes Administrator Region 11 U.S. Nuclear Regulatory Commission Marquis One Plaza 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. Klos Project Manager (McGuire)
U.S. Nuclear Regulatory Commission Mail Stop O-9-E3 11555 Rockville Pike Rockville, MD 20852 Chris Safouri NRG Senior Resident Inspector McGuire Nuclear Station
Attachment Page 1 of 3 Special Report 370-2023-001 Requirement McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual Section 16.2.5 states "Failure to meet a Testing Requirement, whether such failure is experienced during the performance of the Testing Requirement or between performances of the Testing Requirement, shall be failure to meet the Commitment. Additionally, SLC 16.2.6 states "The specified Frequency for each Testing Requirement is met if the Test is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified Frequency is met.
SLC 16.7.1, ATWS/AMSAC, has the following Commitment: The ATWS/AMSAC system shall be FUNCTIONAL in Mode 1 above 40% Reactor Thermal Power (RTP).
If the ATWS/AMSAC system is non-functional in Mode 1 above 40% RTP (Condition A), then Required Action A.1 or Required Action A.2 applies. Required Action A.1 states "Restore the ATWS/AMSAC system to functional status." The Completion Time (CT) for Required Action A.1 is 7 days. Required Action A.2 states "Prepare and submit a Special Report outlining the cause of the malfunction and plans for restoring the system to functional status." The CT for Required Action A.2 is 37 days.
There is one Testing Requirement (TR) associated with SLC 16.7.1. TR 16.7.1.1 states "Perform a Channel Operational Test on the ATWS/AMSAC system." The Frequency for TR 16.7.1.1 is 18 months.
Background
The AMSAC design is based on conditions that indicate a loss of main feedwater event which, if accompanied by a failure of the reactor trip system (RTS) to scram, leads to overpressurization of the Reactor Coolant System. The Unit 2 system monitors both main feedwater pumps for operating status. It also monitors the position of the main feedwater control valves (2CF32AB, 2CF23AB, 2CF20AB, 2CF17AB), the main feedwater control bypass valves (2CF104AB, 2CF105AB, 2CF106AB, 2CF107AB), and the main feedwater isolation valves (2CF35AB, 2CF30AB, 2CF28AB, 2CF26AB).
AMSAC actuation will occur if (1) both main feedwater pumps trip or (2) the main feedwater flow to the steam generators (3 out of 4 logic) is blocked due to inadvertent valve closure. When an actuation occurs, the AMSAC circuitry will perform the following:
Attachment Page 2 of 3 The actuation of the AMSAC system on loss of both main feedwater pumps is achieved by three pressure switches which monitor the hydraulic control oil pressure to the stop valves for each turbine. Each of the feedwater pump turbine stop valves closes whenever there is a trip of the feedwater pump turbine. These pressure switches monitor the hydraulic oil pressure holding the stop valves open. Whenever the pressure switches sense a loss of pressure, indicative of a turbine trip, a two out-of-three logic circuit will actuate. If both pumps are tripped, the AMSAC circuitry will actuate.
Main feedwater isolation valve limit switches are set at the full closed valve position since these valves are operated as full open/closed valves only. The control valve signal is interlocked with the bypass valve signal such that the control valve must be less than 25% open and the bypass valve must be less than 100% open. If these two conditions exist for more than 30 seconds, or if the containment isolation valve closes, then a blocked flow path signal is generated. A 3-out-of-4 blocked flow path logic circuit will actuate the AMSAC circuitry.
Event Description In accordance with SLC 16.2.5, the Unit 2 ATWS/AMSAC system was declared nonfunctional on August 18, 2023, following discovery that a portion of the Channel Operational Test that implements TR 16. 7.1.1 was not performed within 1.25 times its specified 18-month Frequency.
Specifically, preventative maintenance tasks required by Work Order (WO) 20541778 were not performed on main feedwater isolation valve 2CF35AB during the Unit 2 spring 2023 refueling outage. These preventative maintenance tasks included actuator seal replacement, limit switch setup, and functional tests.
Causal Factors According to Action Request 02460345, the preventative maintenance tasks required by Work Order (WO) 20541778 were not performed on main feedwater isolation valve 2CF35AB during the Unit 2 spring 2023 refueling outage due to a lack of necessary parts. Action Request 02483599 was generated to document the failure to perform TR 16. 7.1.1 within 1.25 times its specified 18-month Frequency, perform an Organizational Programmatic Checklist, and develop actions to resolve the issue. At the time of this Special Report, the Organizational Programmatic Checklist had not been completed. Once completed, the Organizational Programmatic Checklist will be retrievable under Action Request 02483599.
Restoration Plans TR 16. 7 .1.1, including limit switch setup of main feedwater isolation valve 2CF35AB, is planned to be performed during the Unit 2 fall 2024 refueling outage. Following satisfactory performance of TR 16. 7.1.1 and prior to entering Mode 1 above 40% RTP, the Unit 2 ATWS/AMSAC system will be declared functional.
Attachment Page 3 of 3 Safety Significance The Unit 2 ATWS/AMSAC system was declared nonfunctional because TR 16. 7.1.1 was not performed within 1.25 times its specified 18-month Frequency. Consistent with the Technical Specification Bases for SR 3.0.3, the safety significance associated with a delay in completing a required surveillance includes recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the requirements.
Furthermore, the probability of system failure is considered low based on the previous work history and the function these limit switches perform. The limit switches are not cycled often since 2CF35AB is a Containment Isolation Valve. Therefore, wear and drift are not a factor.
Also, these limit switches have gold plated contacts which are resistant to oxidation and provide assurance that, if actuated, the circuit will operate as expected.
Based on the probability of failure and consequences, the overall risk to the station is considered low. This event is of no significance with respect to the health and safety of the public.