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| {{#Wiki_filter:.DUKEsteven D. CappsivJ~DUKEVice President | | {{#Wiki_filter:.DUKEsteven D. Capps ivJ~DUKEVice President',., -ENERGYMoGuire Nucl ear Station Duke Energy MG01VP I112700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com 10 CFR 50.90 August 11, 2015 Serial: MNS-1 5-062 U.S. Nuclear Regulatory Commission Washington, DC 20555-00 1 ATTENTION: |
| ',., -ENERGYMoGuire Nucl ear StationDuke EnergyMG01VP I112700 Hagers Ferry RoadHuntersville, NC 28078o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com 10 CFR 50.90August 11, 2015Serial: MNS-1 5-062U.S. Nuclear Regulatory Commission Washington, DC 20555-00 1ATTENTION: | | Document Control Desk Duke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Renewed License Nos. NPF-9 and NPF-17 |
| Document Control DeskDuke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station, Units 1 and 2Docket Nos. 50-369 and 50-370Renewed License Nos. NPF-9 and NPF-17 | |
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| ==Subject:== | | ==Subject:== |
| | | Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (NSWS) Degraded Condition (TAC NOS. MF6409 AND MF6410)By letter dated June 30, 2015, Duke Energy requested a license amendment for the Renewed Facility Operating Licenses (FOL) and Technical Specifications (TS) for the McGuire Nuclear Station, Units 1 and 2, to allow temporary changes to TS 3.5.2, Emergency Core Cooling System (ECCS) -Operating; TS 3.6.6, Containment Spray System (CSS); TS 3.7.5, Auxiliary Feedwater (AFW) System; TS 3.7.6, Component Cooling Water (CCW) System; TS 3.7.7, Nuclear Service Water System (NSWS); TS 3.7.9, Control Room Area Ventilation System (CRAVS); TS 3.7.11, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES), and TS 3.8.1, AC Sources- Operating. |
| Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (NSWS) Degraded Condition (TACNOS. MF6409 AND MF6410)By letter dated June 30, 2015, Duke Energy requested a license amendment for the RenewedFacility Operating Licenses (FOL) and Technical Specifications (TS) for the McGuire NuclearStation, Units 1 and 2, to allow temporary changes to TS 3.5.2, Emergency Core CoolingSystem (ECCS) -Operating; TS 3.6.6, Containment Spray System (CSS); TS 3.7.5, Auxiliary Feedwater (AFW) System; TS 3.7.6, Component Cooling Water (CCW) System; TS 3.7.7,Nuclear Service Water System (NSWS); TS 3.7.9, Control Room Area Ventilation System(CRAVS); | | By letter dated July 27, 2015, Nuclear RegulatorY Commission (NRC) Staff requested additional information (RAI) needed to complete their review of the proposed LAR. The enclosure provides Duke Energy's responses to the RAI questions and contains no additional regulatory commitments. |
| TS 3.7.11, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES), | | Pursuant to 10CFR50.91, 'a copy of this LAR has been forwarded to the appropriate North Carolina state officials. |
| and TS3.8.1, AC Sources-Operating. | | Please direct any comments or questions regarding this submittal to George Murphy at (980) 875-5715. |
| By letter dated July 27, 2015, Nuclear RegulatorY Commission (NRC) Staff requested additional information (RAI) needed to complete their review of the proposed LAR. The enclosure providesDuke Energy's responses to the RAI questions and contains no additional regulatory commitments. | |
| Pursuant to 10CFR50.91, | |
| 'a copy of this LAR has been forwarded to the appropriate NorthCarolina state officials. | |
| Please direct any comments or questions regarding this submittal to George Murphy at(980) 875-5715. | |
| J. JS Nuclear Regulatory Commission | | J. JS Nuclear Regulatory Commission |
| -.YAugust 11, 2015Page 2I declare under penalty of perjury that the foregoing is true and correct. | | -.YAugust 11, 2015 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on August 11, 2015.Sincerely, Steven D. Capps |
| Executed onAugust 11, 2015.Sincerely, Steven D. Capps | |
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| ==Enclosure:== | | ==Enclosure:== |
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| Response to Request for Additional Information 4.UtS Nuclear Regulatory Commission August 11, 2015Page 3cc wI/Attachments: | | Response to Request for Additional Information 4.UtS Nuclear Regulatory Commission August 11, 2015 Page 3 cc wI/Attachments: |
| V. M. McCreeAdministrator, Region IlU.S. Nuclear Regulatory Commission Marquis One Tower245 Peachtree Center Ave., NE, Suite 1200Atlanta, GA 30303-1257 J. ZeilerNRC Senior Resident Inspector McGuire Nuclear StationG. E. Miller, Project ManagerU.S. Nuclear Regulatory Commission 11555 Rockville PikeMail Stop 0-8 G9ARockville, MD 20852-2738 W. L. Cox, Ill, Section ChiefNorth Carolina Department of Environment and Natural Resources Division of Environmental HealthRadiation Protection Section1645 Mail Service CenterRaleigh, NC 27699-1 645 AEnclosure Response to Request for Additional Information NRC Request for Additional Information: | | V. M. McCree Administrator, Region Il U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station G. E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 W. L. Cox, Ill, Section Chief North Carolina Department of Environment and Natural Resources Division of Environmental Health Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1 645 A Enclosure Response to Request for Additional Information NRC Request for Additional Information: |
| 1.The proposed footnotes allow partial usage of the extra 14-day completion time over thecourse of multiple entries into the action statement. | | 1.The proposed footnotes allow partial usage of the extra 14-day completion time over the course of multiple entries into the action statement. |
| Multiple entries into the actionstatement seems inconsistent with the planned diagnostic and corrective work evolution described in the submittal. | | Multiple entries into the action statement seems inconsistent with the planned diagnostic and corrective work evolution described in the submittal. |
| Please iustify why it is necessary to allow partial usage of the extra 14 days.Duke Energy Response: | | Please iustify why it is necessary to allow partial usage of the extra 14 days.Duke Energy Response: MNS expects to inspect the obstruction within the normal TS 72 hour completion time and gain additional information that can be used to remove the obstruction at a later date. The information acquired will be used to compile the best equipment and resources to remove the obstruction to minimize total system unavailability. |
| MNS expects to inspect the obstruction within the normal TS 72 hour completion time andgain additional information that can be used to remove the obstruction at a later date. Theinformation acquired will be used to compile the best equipment and resources to removethe obstruction to minimize total system unavailability. | | However, there is a possibility that the inspection may determine that some type of margin enhancement action is prudent. In this case, MoGuire will take the action using some portion of the 14 day extension. |
| : However, there is a possibility thatthe inspection may determine that some type of margin enhancement action is prudent.
| | Additionally, the inspection may also indicate that the.obstruction can be easily removed with available equipment and resources, in which case, McGuire will use the 14 day extension as needed to remove the obstruction. |
| Inthis case, MoGuire will take the action using some portion of the 14 day extension.
| | Finally, the 14 day extension will not add additional time to the unavailability time managed by the maintenance rule.2. The submittal does not address why this maintenance evolution cannot be performed when one unit is in a refueling outage and, as such, would potentially represent a lower risk configuration and could afford additional time to respond to an event on the shutdown unit.Please justify why this maintenance evolution is not more appropriately performed coincident with a refueling outage of one of the units.Duke Energy Response: Incorporation of the 'A' NSWS SNSWP piping work scope into the refueling outage of one unit would unnecessarily increase the risk of the evolution. |
| Additionally, the inspection may also indicate that the.obstruction can be easily removedwith available equipment and resources, in which case, McGuire will use the 14 dayextension as needed to remove the obstruction. | | The inlet and outlet isolation valves for both units have shared power supplies that would be at greater risk during an outage. The compensatory measures to protect an array of redundant system trains and shared systems would also be at greater risk during an outage. Additionally, the outage would reduce station focus on the A NSWS SNSWP piping work scope due to the number of activities in the outage.The pre-activity defense in depth actions for aligning 'B' Train NSWS to its ESFAS suction source and maintaining the 'A' NSWS Train aligned to Lake Norman make the system fully functional on both Units 1 and 2 for all operating design basis events and analyzed accidents except an earthquake that damages the Lake Norman dam or associated Low Page 1 of 2 |
| : Finally, the 14 day extension will not addadditional time to the unavailability time managed by the maintenance rule.2. The submittal does not address why this maintenance evolution cannot be performed whenone unit is in a refueling outage and, as such, would potentially represent a lower riskconfiguration and could afford additional time to respond to an event on the shutdown unit.Please justify why this maintenance evolution is not more appropriately performed coincident with a refueling outage of one of the units.Duke Energy Response:
| | .pA A Level Intake (LLI). The dam and LLI were originally designed for an Operating Basis Earthquake (OBE).The probability and risk from an OBE during the 14 day extended completion time window is very low as discussed in the LAR. In addition, more recent analysis demonstrates that the Cowan's Ford Dam and LLI supply to the 'A' Train NSWS would survive an OBE and is rugged enough to withstand a Safe Shutdown Earthquake (SSE).The 'B' Train NSWS remains operable and defense in depth guidance is available for a beyond design basis total loss of NSWS flow.Again, the 14 day extension will not add additional time to the unavailability time managed by the maintenance rule.3. The submittal indicates that requested need date is October 31, 2015; however, the proposed expiration date for the TS footnote is December 31, 2016.Given the implied urgency of the requested need date, the NRC staff requests that Duke provide additional iustification for allowing the temporary completion time extension to remain valid until December 31, 2016.Duke Energy Response: As indicated in the response to question 1 above, MNS expects to inspect the obstruction within the normal TS 72 hour completion time and gain additional information that can be used to remove the obstruction at a later date. The information acquired will be used to compile the best equipment and resources to remove the obstruction to minimize total system unavailability. |
| Incorporation of the 'A' NSWS SNSWP piping work scope into the refueling outage of oneunit would unnecessarily increase the risk of the evolution. | | Equipment and resources identified during the inspection may not be immediately available due to long lead times. The final removal work schedule will be defined based on the associated lead times. However, equipment and resources will be identified and acquired as necessary to support the December 31, 2016, expiration date.Page 2 of 2}} |
| The inlet and outlet isolation valves for both units have shared power supplies that would be at greater risk during anoutage. The compensatory measures to protect an array of redundant system trains andshared systems would also be at greater risk during an outage. Additionally, the outagewould reduce station focus on the A NSWS SNSWP piping work scope due to the numberof activities in the outage.The pre-activity defense in depth actions for aligning | |
| 'B' Train NSWS to its ESFAS suctionsource and maintaining the 'A' NSWS Train aligned to Lake Norman make the system fullyfunctional on both Units 1 and 2 for all operating design basis events and analyzedaccidents except an earthquake that damages the Lake Norman dam or associated LowPage 1 of 2 | |
| .pA ALevel Intake (LLI). The dam and LLI were originally designed for an Operating BasisEarthquake (OBE).The probability and risk from an OBE during the 14 day extended completion time windowis very low as discussed in the LAR. In addition, more recent analysis demonstrates thatthe Cowan's Ford Dam and LLI supply to the 'A' Train NSWS would survive an OBE and isrugged enough to withstand a Safe Shutdown Earthquake (SSE).The 'B' Train NSWS remains operable and defense in depth guidance is available for abeyond design basis total loss of NSWS flow.Again, the 14 day extension will not add additional time to the unavailability time managedby the maintenance rule.3. The submittal indicates that requested need date is October 31, 2015; however, theproposed expiration date for the TS footnote is December 31, 2016.Given the implied urgency of the requested need date, the NRC staff requests thatDuke provide additional iustification for allowing the temporary completion timeextension to remain valid until December 31, 2016.Duke Energy Response: | |
| As indicated in the response to question 1 above, MNS expects to inspect the obstruction within the normal TS 72 hour completion time and gain additional information that can beused to remove the obstruction at a later date. The information acquired will be used tocompile the best equipment and resources to remove the obstruction to minimize totalsystem unavailability. | |
| Equipment and resources identified during the inspection may not be immediately available due to long lead times. The final removal work schedule will be defined based on theassociated lead times. However, equipment and resources will be identified and acquiredas necessary to support the December 31, 2016, expiration date.Page 2 of 2}} | |
Letter Sequence Response to RAI |
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MONTHYEARML13304B4452013-10-28028 October 2013 Revised License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Project stage: Request ML13351A3432013-12-19019 December 2013 Acceptance of Requested Licensing Action License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Project stage: Acceptance Review ML14127A4622014-05-12012 May 2014 Request for Additional Information Regarding License Amendment Request to Modify Specification 3.8.4 Setpoint Project stage: RAI MNS-14-045, Responses to Request for Additional Information Related to License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Dated October 28, 20132014-06-0303 June 2014 Responses to Request for Additional Information Related to License Amendment Request for One-Time Change to Technical Specification 3.8.4, DC Sources-Operating for Battery Replacement Dated October 28, 2013 Project stage: Response to RAI ML14178B2322014-07-14014 July 2014 Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint Project stage: RAI ML14231A6342014-09-10010 September 2014 Issuance of Amendments Regarding Technical Specification 3.8.4, DC Sources-Operating, Project stage: Approval ML15202A6612015-07-27027 July 2015 Acceptance Review of License Amendment Request Temporary Changes to Technical Specifications for Correction of Nuclear Service Water System Degraded Condition Project stage: Acceptance Review ML15196A3862015-08-0404 August 2015 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing and Order Imposing Procedures for Document Access To.. Project stage: Other MNS-15-062, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition2015-08-11011 August 2015 Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition Project stage: Response to RAI ML15196A6162015-08-13013 August 2015 Duke Energy Carolinas, LLC, McGuire Nuclear Station, Units 1 and 2 - License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene; Order Project stage: Other ML15243A4082015-08-28028 August 2015 NRR E-mail Capture - Draft RAI for Nsws Temp AOT Extension Project stage: Draft RAI ML15252A2762015-09-14014 September 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension Project stage: RAI MNS-15-073, Response to NRC Letter Dated August 27, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension2015-09-24024 September 2015 Response to NRC Letter Dated August 27, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension Project stage: Request 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 Project stage: Request ML15289A5552015-10-26026 October 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension Project stage: RAI 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. Project stage: Request 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 Project stage: Response to RAI 2015-12-07
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Category:Letter
MONTHYEARIR 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 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 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 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 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 IR 05000369/20234202023-07-24024 July 2023 Security Baseline Inspection Report 050003692023420 and 050003702023420 ML23206A0092023-07-24024 July 2023 William B. McGuire Nuclear Station Operator Licensing Written Examination Approval 05000369/2023301 and 05000370/2023301 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 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 IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 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 IR 05000369/20220062023-03-0101 March 2023 Annual Assessment Letter for McGuire Nuclear Station Units 1 and 2 (NRC Inspection Report 05000369/2022006 and 05000370 2022006) IR 05000369/20220042023-01-30030 January 2023 Mcguire Nuclear Station - Integrated Inspection Report 05000369/2022004 and 05000370/2022004 IR 05000369/20224202023-01-11011 January 2023 Security Baseline Inspection Report 05000369/2022420 and 05000370/2022420 ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22347A1512022-12-13013 December 2022 William B. Mcguire Nuclear Station Notification of Licensed Operator Initial Examination 05000369/2023301 and 05000370/2023301 ML22340A6662022-12-0808 December 2022 Summary of November 30, 2022, Public Meeting with Duke Energy Carolinas, LLC for McGuire Nuclear Station, Units 1 & 2 Proposed LAR to Adopt TSTF-505, Rev. 2 and 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems ML22290A1012022-11-29029 November 2022 Issuance of Amendment Nos. 326 and 305, Regarding Changes to Technical Specification 3.4.3, Reactor Coolant System Pressure Temperature Limits ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000369/20220032022-10-27027 October 2022 Integrated Inspection Report 05000369/2022003 and 05000370/2022003 IR 05000369/20220112022-09-29029 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000369/2022011 and 05000370/2022011 ML22266A0782022-09-26026 September 2022 William B. Mcguire Nuclear Station, Unit 2 Pressurizer Power Operated Relief Valve Relief Request ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition IR 07200038/20220012022-09-12012 September 2022 Operation of an Independent Spent Fuel Storage Installation Report 07200038/2022001 ML22230B6132022-09-0101 September 2022 Review of the Draft Environmental Assessment and Finding of No Significant Impact for Brunswick Steam Electric Plant and McGuire Nuclear Station Independent Spent Fuel Storage Installations Decommissioning Funding Plans IR 05000369/20220052022-08-29029 August 2022 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 NRC Inspection Report 05000369/2022005 and 05000370/2022005 IR 05000369/20220022022-07-26026 July 2022 Integrated Inspection Report 05000369/2022002 and 05000370/2022002 ML22215A2502022-07-25025 July 2022 EN 55960 - Update - Curtiss Wright ML22164A0362022-07-19019 July 2022 Mcguire Nuclear Station, Units 1 and 2; Issuance of Amendments to Revise the Conditional Exemption of the End-Of-Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) Public ML22175A0162022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML22046A0222022-06-14014 June 2022 Issuance of Amendments to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML22111A3112022-05-16016 May 2022 Letter Issuing Exemption to McGuire IR 05000369/20224012022-05-12012 May 2022 Cyber Security Inspection Report 05000369/2022401 and 05000370/2022401 2024-01-31
[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
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.DUKEsteven D. Capps ivJ~DUKEVice President',., -ENERGYMoGuire Nucl ear Station Duke Energy MG01VP I112700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com 10 CFR 50.90 August 11, 2015 Serial: MNS-1 5-062 U.S. Nuclear Regulatory Commission Washington, DC 20555-00 1 ATTENTION:
Document Control Desk Duke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 Renewed License Nos. NPF-9 and NPF-17
Subject:
Response to Request for Additional Information Regarding License Amendment Request (LAR) for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (NSWS) Degraded Condition (TAC NOS. MF6409 AND MF6410)By letter dated June 30, 2015, Duke Energy requested a license amendment for the Renewed Facility Operating Licenses (FOL) and Technical Specifications (TS) for the McGuire Nuclear Station, Units 1 and 2, to allow temporary changes to TS 3.5.2, Emergency Core Cooling System (ECCS) -Operating; TS 3.6.6, Containment Spray System (CSS); TS 3.7.5, Auxiliary Feedwater (AFW) System; TS 3.7.6, Component Cooling Water (CCW) System; TS 3.7.7, Nuclear Service Water System (NSWS); TS 3.7.9, Control Room Area Ventilation System (CRAVS); TS 3.7.11, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES), and TS 3.8.1, AC Sources- Operating.
By letter dated July 27, 2015, Nuclear RegulatorY Commission (NRC) Staff requested additional information (RAI) needed to complete their review of the proposed LAR. The enclosure provides Duke Energy's responses to the RAI questions and contains no additional regulatory commitments.
Pursuant to 10CFR50.91, 'a copy of this LAR has been forwarded to the appropriate North Carolina state officials.
Please direct any comments or questions regarding this submittal to George Murphy at (980) 875-5715.
J. JS Nuclear Regulatory Commission
-.YAugust 11, 2015 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on August 11, 2015.Sincerely, Steven D. Capps
Enclosure:
Response to Request for Additional Information 4.UtS Nuclear Regulatory Commission August 11, 2015 Page 3 cc wI/Attachments:
V. M. McCree Administrator, Region Il U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station G. E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 W. L. Cox, Ill, Section Chief North Carolina Department of Environment and Natural Resources Division of Environmental Health Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1 645 A Enclosure Response to Request for Additional Information NRC Request for Additional Information:
1.The proposed footnotes allow partial usage of the extra 14-day completion time over the course of multiple entries into the action statement.
Multiple entries into the action statement seems inconsistent with the planned diagnostic and corrective work evolution described in the submittal.
Please iustify why it is necessary to allow partial usage of the extra 14 days.Duke Energy Response: MNS expects to inspect the obstruction within the normal TS 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time and gain additional information that can be used to remove the obstruction at a later date. The information acquired will be used to compile the best equipment and resources to remove the obstruction to minimize total system unavailability.
However, there is a possibility that the inspection may determine that some type of margin enhancement action is prudent. In this case, MoGuire will take the action using some portion of the 14 day extension.
Additionally, the inspection may also indicate that the.obstruction can be easily removed with available equipment and resources, in which case, McGuire will use the 14 day extension as needed to remove the obstruction.
Finally, the 14 day extension will not add additional time to the unavailability time managed by the maintenance rule.2. The submittal does not address why this maintenance evolution cannot be performed when one unit is in a refueling outage and, as such, would potentially represent a lower risk configuration and could afford additional time to respond to an event on the shutdown unit.Please justify why this maintenance evolution is not more appropriately performed coincident with a refueling outage of one of the units.Duke Energy Response: Incorporation of the 'A' NSWS SNSWP piping work scope into the refueling outage of one unit would unnecessarily increase the risk of the evolution.
The inlet and outlet isolation valves for both units have shared power supplies that would be at greater risk during an outage. The compensatory measures to protect an array of redundant system trains and shared systems would also be at greater risk during an outage. Additionally, the outage would reduce station focus on the A NSWS SNSWP piping work scope due to the number of activities in the outage.The pre-activity defense in depth actions for aligning 'B' Train NSWS to its ESFAS suction source and maintaining the 'A' NSWS Train aligned to Lake Norman make the system fully functional on both Units 1 and 2 for all operating design basis events and analyzed accidents except an earthquake that damages the Lake Norman dam or associated Low Page 1 of 2
.pA A Level Intake (LLI). The dam and LLI were originally designed for an Operating Basis Earthquake (OBE).The probability and risk from an OBE during the 14 day extended completion time window is very low as discussed in the LAR. In addition, more recent analysis demonstrates that the Cowan's Ford Dam and LLI supply to the 'A' Train NSWS would survive an OBE and is rugged enough to withstand a Safe Shutdown Earthquake (SSE).The 'B' Train NSWS remains operable and defense in depth guidance is available for a beyond design basis total loss of NSWS flow.Again, the 14 day extension will not add additional time to the unavailability time managed by the maintenance rule.3. The submittal indicates that requested need date is October 31, 2015; however, the proposed expiration date for the TS footnote is December 31, 2016.Given the implied urgency of the requested need date, the NRC staff requests that Duke provide additional iustification for allowing the temporary completion time extension to remain valid until December 31, 2016.Duke Energy Response: As indicated in the response to question 1 above, MNS expects to inspect the obstruction within the normal TS 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time and gain additional information that can be used to remove the obstruction at a later date. The information acquired will be used to compile the best equipment and resources to remove the obstruction to minimize total system unavailability.
Equipment and resources identified during the inspection may not be immediately available due to long lead times. The final removal work schedule will be defined based on the associated lead times. However, equipment and resources will be identified and acquired as necessary to support the December 31, 2016, expiration date.Page 2 of 2