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Category:Letter
MONTHYEARIR 05000369/20240032024-11-0404 November 2024 Integrated Inspection Report 05000369/2024003 and 05000370/2024003 ML24303A4212024-10-30030 October 2024 Mcguire Nuclear Station, Units 1 & 2, Notification of an NRC Fire Protection Team Inspection FPTI NRC 05000369/2025010, 05000370/2025010 and Request for Information RFI IR 05000369/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 05000369/LER-1923-001, Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error2023-12-13013 December 2023 Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection – U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20234012023-08-0404 August 2023 – Security Baseline Inspection Report 05000369/2023401 and 05000370/2023401 (OUO-SRI) Cover IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station – Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 IR 05000369/20234202023-07-24024 July 2023 – Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A2712023-06-20020 June 2023 William B. McGuire Nuclear Station, Unit 1 - Relief Request Impractical Reactor System Welds ML23237A2672023-06-13013 June 2023 June 13, 2002 - Meeting Announcement - McGuire and Catawba Nuclear Stations 50-369, 50-370 and 50-413, 50-414 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23124A0862023-05-0303 May 2023 Cycle 29, Revision 1, Core Operating Limits Report (COLR) IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23094A1832023-04-18018 April 2023 Audit Plan TSTF-505, Rev. 2, RITSTF Initiative 4B & 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors (EPIDs L-2023-LLA-0021 & L-2023-LLA-0022) ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility 2024-08-26
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-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-23-0136, 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-23-0142, 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-23-0076, 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-23-0025, 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-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-22-0102, 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-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative RA-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-10-0404 October 2021 Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage2021-01-29029 January 2021 Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2020-04-0202 April 2020 Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.12019-04-0808 April 2019 Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 22019-03-0707 March 2019 Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-19-0005, Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2019-01-30030 January 2019 Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A RA-18-0229, Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.12018-12-0303 December 2018 Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1 RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles2018-11-0101 November 2018 Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles ML18191A5642018-07-10010 July 2018 Attachment 3 - Response to NRC Request for Additional Information MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles2018-07-0303 July 2018 Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles ML20052D9362018-07-0303 July 2018 Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-12-12012 December 2017 Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML17349A1572017-12-12012 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Temporary Changes to Technical Specifications to Address the 'A' Train Nuclear Service Water System Non-Conforming Condition RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal RA-17-0030, Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-06-0808 June 2017 Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017 Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. ML16294A2542016-10-13013 October 2016 Response to Request for Additional Information Regarding Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation ML16244A0602016-08-18018 August 2016 Response to Request for Addition Information to RR 16-MN-003 MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-0032016-08-18018 August 2016 Response to Request for Additional Information to Relief Request 16-MN-003 MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML16230A0062016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request to Technical Specification 3.6.13, Ice Condenser Doors RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations2016-07-14014 July 2016 Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information2016-06-30030 June 2016 License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information MNS-16-023, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications2016-03-16016 March 2016 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications ML16056A2422016-02-18018 February 2016 Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Change the Emergency Plan to Upgrade Emergency Action Levels Based on NEI 99-01, Revision 6 MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension2016-02-10010 February 2016 Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-0404 February 2016 Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. MNS-16-009, Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c)2016-02-0404 February 2016 Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c) RA-16-0006, Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions2016-02-0101 February 2016 Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions MNS-16-003, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation2016-01-0707 January 2016 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation ML15343A0122015-12-0707 December 2015 Response to NRC Letter Dated 10/26/2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension. MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System2015-11-13013 November 2015 Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension2015-10-0808 October 2015 Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension MNS-15-077, Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2015-10-0808 October 2015 Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. 2023-07-07
[Table view] |
Text
e._(~ DUKE Steven D. Capps Vice President
~ ENERGY McGuire Nuclear Station Duke Energy MGOlVP I 12700 Hagers Ferry Road Huntersville, NC 28078 0: 980.875.4805 f: 980.875.4809 Steven. Ca pps@duke-energy.com August 11, 2016 Serial No.: MNS-16-063 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Duke Energy Carolinas, LLC (Duke Energy)
McGuire Nuclear Station (MNS), Units 1 and 2 Docket Numbers 50-369 and 50-370 Renewed License Numbers NPF-9 and NPF-17
Subject:
License Amendment Request to Technical Specification (TS) 3.6.13, "Ice Condenser Doors" In a letter dated March 24, 2016, Duke Energy submitted a License Amendment Request (LAR) to revise TS 3.6.13, "Ice Condenser Doors." By email dated July 12, 2016, the NRC submitted Requests for Additional Information (RAls) related to this LAR. Enclosure 1 of this letter provides Duke Energy's response to those RAls.
This letter contains no regulatory commitments.
Pursuant to 10 CFR 50.91, a copy of this letter has been forwarded to the appropriate North Carolina state officials.
Please direct any questions you may have in this matter to Brian Richards at (980) 875-5171.
I declare under penalty of perjury that the foregoing is true and correct. Executed on August 11, 2016.
Sincerely, ltO~
Steven D. Capps Enclosure 1: Response to Requests for Additional Information www.duke-energy.com
U.S. Nuclear Regulatory Commission Serial Number MNS-16-063 Page 2 xc with Attachments C. Haney Regional Administrator, Region II U. S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave. NE, Suite 1200 Atlanta, GA 30303-1257 A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station Electronic copies:
G. E. Miller, Project Manager Ed.Miller@nrc.gov V. Sreenivas, Interim Project Manager V.Sreenivas@nrc.gov W. L. Cox, Ill, Section Chief North Carolina Department of Environment and Natural Resources lee.cox@dhhs.nc.gov
Enclosure 1 Response to Requests for Additional Information
Enclosure 1 Page 2 of 6 Balance of Plants Branch (SBPB):
- 1. Does a non-functional ice condenser lower inlet door (LID) position limit switch (an invalid open alarm input) render a LID inoperable?
Surveillance Requirement (SR) 3.6.13.1 specifies use of the Inlet Door Position Monitoring System to verify that all inlet doors indicate closed. The inability to meet the SR due to an invalid open alarm input renders the affected LIDs inoperable, which in turn requires entry into Condition B of Technical Specification (TS) 3.6.13, "Ice Condenser Doors."
- 2. The LAR states that a License Amendment is needed to preclude an unnecessary plant shutdown caused by an invalid "ICE COND LOWER INLET DOORS OPEN" alarm. This alarm can be the result of a single invalid LID position indication. Justify the proposed TS change providing no limit to the number of LIDs with invalid position indication.
McGuire Response:
TS 3.6.13 has a note stating that a separate condition entry is allowed for each ice condenser door. As currently written, all LIDs are allowed to be inoperable for up to 14 days, as long as the inoperability is not due to the door being physically restrained from opening. This 14 day completion time does, however, require the ice bed temperature to be monitored every four hours.
The proposed amendment is intended to provide additional flexibility to the TS, and no changes were made to the note allowing separate condition entries for each door. For a case where a LID is inoperable solely because of an invalid open indication, the requested change would allow McGuire ~o remain online if any LID affected by the invalid indication is verified closed every 14 days and as long as ice bed temperature is monitored every four hours. Unlike a case
- where a LID is actually open, no air leakage occurs when the LID is closed, so the number of LIDs affected by an invalid open position indication is inconsequential. Also, a door with an invalid open position indication is still capable of opening as required by plant conditions.
Therefore, no limit to the number of LIDs with invalid position indication is warranted. (
Enclosure 1 Page 3 of 6
- 3. The LAR indicates that SR 3. 6. 13. 1 requires verification that al/ lower inlet doors indicate closed by the Inlet Door Position Monitoring System and that this is normally performed in the CR by observance of the associated annunciator alarm status. In the event of one or more LID invalid door open alarm inputs the open/closed status verification of the remaining LfDs would be performed using the local door position display panel located in upper containment on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> frequency per TS SR 3. 6. 13. 1, in accordance with what the Surveillance Frequency Control Program allowed for a maximum interval at that time. The local panel provides zone by zone indication of all 8 doors in a zone being shut or at least one door in a zone being open.
- a. Would this change in SR 3.6.13.1 method verify closed position indication for all other L/Ds or just all other L/Ds in unaffected zones? Would the other L/Ds in the affected zone(s) be remote visually verified closed on the 14 day interval?
- b. Justify extended operation with the control room annunciator alarm locked in and LID position monitoring once each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or longer instead of continuous.
McGuire Response:
- a. Since the local door position display panel, located in upper containment, provides zone-by-zone indication, each zone that indicates closed is considered unaffected by an invalid open indication. The proposed LAR states that SR 3.6.13.1 will be met for unaffected LID indications using this local display panel.
Verification of door position for all LIDs in zones with an invalid open indication would be performed per the requested change to Condition 8 of TS 3.6.13. This change specifies using an alternate means of verifying door closure once every 14 days. If dose concerns prohibit normal access to inspect the LIDs, a remote video camera system may be used.
- b. SR 3.6.13.1 is performed in accordance with the Surveillance Frequency Control Program. Currently, this surveillance is performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The control room annunciator alarm is an output of the Inlet Door Position Monitoring System and is for operational use. When any of the LIDs are not fully closed, the annunciator will come into alarm status, and the annunciator response includes checking the door monitor system compared to the actual door position.
As documented in Section 3.2 of the proposed LAR, monitoring the ice bed RTDs is an alternate method of checking for the presence of unwanted thermal energy ingress. In the event that an invalid open position signal causes the control room annunciator alarm to be locked in, the unit will have entered Condition 8 of TS 3.6.13, which requires verification that the maximum ice bed temperature is no greater than 27°F once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Existing TS Condition 8 assumes that an ice condenser door is open or inoperable such that air leakage is occurring. In this scenario, the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> verification frequency is justified based on the fact that temperature changes cannot occur rapidly in the ice bed because of the large mass of ice involved. The current TS also allows 14 days to restore an inoperable or open door to operable and closed position because maintaining the temperatures below 27°F prevents any significant loss of ice due to sublimation.
Enclosure 1 Page 4 of 6 McGuire Selected Licensee Commitment (SLC) 16.6.3, "Inlet Door Position Monitoring System,"
requires this position indication system to be functional. As long as the ice bed temperature indication is functional and ice bed temperatures are verified no greater than 27°F every four hours, the SLC allows the Inlet Door Position Monitoring System to be out of service for 14 days.
The proposed change to TS 3.6.13 involves a scenario where an invalid open position indication exists for a LID. In this scenario, no air leakage into the ice condenser exists because the open indication is spurious, and the spurious nature of the indication is re-verified every 14 days.
Since validating ice bed temperatures are within range every four hours is acceptable when some amount of air leakage exists and/or when the Inlet Door Position Monitoring System is out of service, continuously monitoring the local door position display panel is not warranted.
- 4. The proposed TS change does not have a completion time for continued operation with one or more L/Ds with non-functional position limit switch (an invalid open alarm input). Would TS LCO 3. 0.4 permit mode change to a mode of applicability without restoring proper LID position indication function?
McGuire Response:
TS LCO 3.0.4.b provides the option of performing a risk assessment in order to determine the acceptability of entering a mode or other specified condition when an LCO is not met.
Exceptions to TS LCO 3.0.4.b are stated in individual specifications, and TS 3.6.13 does not contain any such prohibition.
Therefore, as long as the risk assessment is acceptable and appropriate risk management actions are established, TS LCO 3.0.4 could be used to permit changing modes while a LID position indication input is not functioning properly.
Enclosure 1 Page 5of6 PRA Operations and Human Factors Branch (APHB): of the March 24, 2016 license amendment request (LAR) contains a marked up revision of REQUIRED ACTION B. 1 which requires operators to "Verify maximum ice bed temperature is~ 27°F" once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
This revision adds a new NOTE (emphasis added): "Required Action B.2.1 applies only when one or more ice condenser lower inlet doors are inoperable due to having an invalid open alarm."
REQUIRED ACTION B.2.1 goes on to state "Verify affected lower inlet door is closed" once per 14 days OR conduct REQUIRED ACTION B.2.2.
The NOTE does not clearly indicate when, or how to determine that the alarm is truly invalid (as opposed to being suspected invalid). REQUIRED ACTION 8.2.1 provides one means for verifying that a suspected invalid alarm is truly invalid (by verifying that the door is truly closed),
however, under some conditions it directs operators away from REQUIRED ACTION B.2.1 without directing them to an alternate m.ethod for verification.
This strategy has the potential for causing complacency in operators similar to what was observed in the Three Mile Island accident (see NUREG/CR-1270 for more information).
Operators knew of a long-standing leak that caused temperature indications on the pressurizer PORV exhaust pipe to be elevated during normal conditions. As a result, operators learned to expect faulted indication and subsequently altered their mental model of the system. During the accident operators ignored, or otherwise misinterpreted, valid temperature indications from the system. As a result, it took operators 138 minutes to come to the conclusion that the PORV was open. If the operators did not have the expectation that temperatures in the PORV exhaust pipe are normally high (and should therefore be ignored), they may have observed the increase in the PORV exhaust pipe temperature and come to the conclusion the PORV was stuck open much sooner and may have prevented the accident.
Please clarify the logic of this TS or revise the TS to ensure that it does not promote operator complacency.
Clarify how it is possible for operators to make the determination that the signal is invalid without performing REQUIRED ACTION 8.2. 1.
Describe how procedures and/or training will be used to ensure that operators do not systematically ignore what they may perceive as a chronically faulted alarm.
McGuire Response:
The proposed revision to TS 3.6.13 Condition B adds a new Required Action, which provides the flexibility to allow continued operation with an inoperable LID. New Required Action B.2.1 verifies once every 14 days that a LID affected by an invalid open position indication is closed.
The note preceding the new proposed Required Action specifies that Required Action B.2.1 is only applicable in the case that a LID is inoperable due to the presence of an invalid open alarm. In other words, this note is not intended to define how st?tion personnel determine that a
Enclosure 1 Page 6 of 6 position indication alarm is invalid. Rather, the note prevents the station from using the revised TS to continue operation except in cases where an invalid open position indication exists.
If TS 3.6.13 Condition 8, as revised by the proposed amendment, is entered as a result of an open LID position indication, the required actions in levels 8.1 and 8.2 must be taken.
Monitoring of ice bed temperatures, as specified by Required Action 8.1, would begin.
Additionally, until operators know that the LID open alarm is invalid, they would have to assume that the door actually is open, which requires restoring the door to operable status and closed position within 14 days per Required Action 8.2.2. This is in accordance with how operators are trained to follow Technical Specifications.
The most likely method of proving that the open position indication is faulty involves using alternate methods to verify that the affected LIDs are closed. Once verified, either physically (if radiation is not excessive) or by remote camera, the first performance of Required Action 8.2.1 will have been completed. In order to continue operation, ice bed temperatures would have to be monitored every four hours, and the affected LIDs would have to continue to be verified closed every 14 days.
Although the control room annunciator for ice condenser door position will remain lit while any LID has an open signal (valid or invalid), the local door position display panel in upper containment can provide a more refined understanding of which doors are affected. This display panel will be used to perform the normal 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> surveillance for the LIDs unaffected by the invalid position indication. If other zones are found with open position indications, TS 3.6.13 Condition B would be entered for the newly affected LIDs, and the appropriate required actions would be taken. By entering the TS and taking the actions specified, the control room operators maintain awareness of plant performance.