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| | number = ML14114A526 | | | number = ML14114A526 |
| | issue date = 04/28/2014 | | | issue date = 04/28/2014 |
| | title = McGuire Nuclear Station, Units 1 and 2: Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint (TAC Nos. MF2741 and MF2742) | | | title = Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint |
| | author name = Miller G E | | | author name = Miller G |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Capps S D | | | addressee name = Capps S |
| | addressee affiliation = Duke Energy Carolinas, LLC | | | addressee affiliation = Duke Energy Carolinas, LLC |
| | docket = 05000369, 05000370 | | | docket = 05000369, 05000370 |
| | license number = NPF-009, NPF-017 | | | license number = NPF-009, NPF-017 |
| | contact person = Miller G E | | | contact person = Miller G |
| | case reference number = TAC MF2741, TAC MF2742 | | | case reference number = TAC MF2741, TAC MF2742 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985 April 28, 2014 SUBJECT: MCGUIRE NUCLEAR STATION, UNITS 1 AND 2: REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION 3.3.2 SETPOINT (TAC NOS. MF2741 AND MF2742) Dear Mr. Capps: By letter dated September 12, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 13262A500), Duke Energy Carolinas, LLC (the licensee) submitted a license amendment request, which requested to modify Technical Specification 3.3.2, "Engineered Safety Features Actuation System (ESFAS) Instrumentation." Specifically, the proposed change would modify the setpoint for Auxiliary Feedwater Pump Suction Transfer in support of your efforts to comply with NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events." The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). On April 23, 2014, the Duke staff indicated that a response to the RAI would be provided by May 23, 2014. If you have any questions, please call me at 301-415-2481. Docket Nos. 50-369 and 50-370 Enclosure: Request for Additional Information cc w/encl: Distribution via Listserv G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 ' . . PROPOSED CHANGES TO TECHNICAL SPECIFICATION 3.3.2 ' IN SUPPORT OF COMPLIANCE WITH NRC ORDER EA-12-049 DOCKET NOS. 50-369 AND 50-370 By letter dated September 12, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 13262A500), Duke Energy Carolinas submitted a license amendment request (LAR) to amend the Technical Specifications (TSs) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," FUNCTION 6.f, "Auxiliary Feedwater Pump Suction Transfer on Suction Pressure-Low (c)" for McGuire Nuclear Station, Units 1 and 2, in support of plant modifications required to achieve compliance with the NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements of Mitigation Strategies for Beyond-Design-Basis External Events;'' dated March 12, 2012. In order for the NRC staff to complete its review of the LAR, the following additional information is requested. 1. In the submittal, Duke stated: The existing safety-related automatic alignment of NSW to the AFW suction is achieved by means of pressure switches which open AC-motor operated valves. The pressure switches are located on the AFW pump suction lines. The AFW MOPs utilize two pressure switches per train (one switch per isolation valve). The TDAFWP utilizes four switches per train. A low pressure signal sensed by two switches on either train will cause the assured NSW supply of water for the pump to be aligned. The NRC staff acknowledges that a low pressure signal sensed by two switches on a train of pressure switches associated with the motor-driven auxiliary feedwater pump will open flow from the service water header to the pump's suction. However, the submittal indicated that the turbine-driven auxiliary feedwater pump has four pressure switches per train. From the description given, it appears that there are actually two trains of two switches in this logic, each train associated with a different nuclear service water header. If this is the situation, the above statement, "A low pressure signal sensed by two switches on either train will cause the assured NSW supply of water for the pump to be aligned," would not be true for all cases for the turbine-driven auxiliary feedwater pump. In this case, only a select two pressure switches of the four switches will open flow from a service water header. The NRC staff requests the licensee to clarify its description of the pressure switch logic associated with the turbine-driven* auxiliary feedwater pump and make any necessary changes. 2. The licensee is proposing different setpoints for the pressure switches on the "2A" motor-driven auxiliary feedwater pumps. The TSs are combined for Unit 1 and Unit 2. Enclosure | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 28, 2014 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985 |
| -2-Figure 1 in Attachment 4 shows some piping configurations are different for the two units, especially where the new "SSS/ELAP" supply of water ties into the suction piping. The NRC staff requests confirmation that the elevation difference for the "2A" driven auxiliary feedwater pumps is 2-feet on both units.
| | |
| Mr .. Steven D. Capps, Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985 April 28, 2014 SUBJECT: MCGUIRE NUCLEAR STATION, UNITS 1 AND 2: REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION 3.3.2 SETPOINT (TAC NOS. MF2741 AND MF2742) Dear Mr. Capps: By letter dated September 12, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML 13262A500), Duke Energy Carolinas, LLC (the licensee) submitted a license amendment request, which requested to modify Technical Specification
| | ==SUBJECT:== |
| * 3.3.2, "Engineered Safety Features Actuation System (ESFAS) Instrumentation." Specifically, the proposed change would modify the setpoint for Auxiliary Feedwater Pump Suction Transfer in support of your efforts to comply with NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events." The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). On April 23, 2014, the Duke staff indicated that a response to the RAI would be provided by May 23, 2014. If you have any questions, please call me at 301-415-2481. Docket Nos. 50-369 and 50-370 Enclosure:* Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION: Public RidsAcrsAcnw_MaiiCTR Resource RidsNrrDssSbpb Resource RidsNrrLASFigueroa Resource ADAMS Accession No ML 14114A526 LPL2-1 R/F Sincerely, /RA/ G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorllpl2-1 Resource RidsNrrPMMcGuire Resource (hard copy) RidsRgn2MaiiCenter Resource OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/DSS/SBPB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME GEMiller SFigueroa GCasto RPascarelli GEM iller DATE 04/28/14 04/28/14 04/07/14 04/28/14 04/28/14 OFFICIAL RECORD COPY
| | MCGUIRE NUCLEAR STATION, UNITS 1 AND 2: REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION 3.3.2 SETPOINT (TAC NOS. MF2741 AND MF2742) |
| }} | | |
| | ==Dear Mr. Capps:== |
| | |
| | By letter dated September 12, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML13262A500), Duke Energy Carolinas, LLC (the licensee) submitted a license amendment request, which requested to modify Technical Specification 3.3.2, "Engineered Safety Features Actuation System (ESFAS) Instrumentation." Specifically, the proposed change would modify the setpoint for Auxiliary Feedwater Pump Suction Transfer in support of your efforts to comply with NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events." |
| | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). On April 23, 2014, the Duke staff indicated that a response to the RAI would be provided by May 23, 2014. |
| | If you have any questions, please call me at 301-415-2481. |
| | G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370 |
| | |
| | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATION 3.3.2 ' |
| | IN SUPPORT OF COMPLIANCE WITH NRC ORDER EA-12-049 DOCKET NOS. 50-369 AND 50-370 By letter dated September 12, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13262A500), Duke Energy Carolinas submitted a license amendment request (LAR) to amend the Technical Specifications (TSs) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," FUNCTION 6.f, "Auxiliary Feedwater Pump Suction Transfer on Suction Pressure- Low (c)" for McGuire Nuclear Station, Units 1 and 2, in support of plant modifications required to achieve compliance with the NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements of Mitigation Strategies for Beyond-Design-Basis External Events;'' dated March 12, 2012. In order for the NRC staff to complete its review of the LAR, the following additional information is requested. |
| | : 1. In the submittal, Duke stated: |
| | The existing safety-related automatic alignment of NSW to the AFW p~mps' suction is achieved by means of pressure switches which open AC-motor operated valves. The pressure switches are located on the AFW pump suction lines. The AFW MOPs utilize two pressure switches per train (one switch per isolation valve). The TDAFWP utilizes four switches per train. A low pressure signal sensed by two switches on either train will cause the assured NSW supply of water for the pump to be aligned. |
| | The NRC staff acknowledges that a low pressure signal sensed by two switches on a train of pressure switches associated with the motor-driven auxiliary feedwater pump will open flow from the service water header to the pump's suction. However, the submittal indicated that the turbine-driven auxiliary feedwater pump has four pressure switches per train. From the description given, it appears that there are actually two trains of two switches in this logic, each train associated with a different nuclear service water header. |
| | If this is the situation, the above statement, "A low pressure signal sensed by two switches on either train will cause the assured NSW supply of water for the pump to be aligned," would not be true for all cases for the turbine-driven auxiliary feedwater pump. |
| | In this case, only a select two pressure switches of the four switches will open flow from a service water header. |
| | The NRC staff requests the licensee to clarify its description of the pressure switch logic associated with the turbine-driven* auxiliary feedwater pump and make any necessary changes. |
| | : 2. The licensee is proposing different setpoints for the pressure switches on the "2A" motor-driven auxiliary feedwater pumps. The TSs are combined for Unit 1 and Unit 2. |
| | Enclosure |
| | |
| | Figure 1 in Attachment 4 shows some piping configurations are different for the two units, especially where the new "SSS/ELAP" supply of water ties into the suction piping. |
| | The NRC staff requests confirmation that the elevation difference for the "2A" motor-driven auxiliary feedwater pumps is 2-feet on both units. |
| | |
| | ML14114A526 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/DSS/SBPB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME GEMiller SFigueroa GCasto RPascarelli GEM iller DATE 04/28/14 04/28/14 04/07/14 04/28/14 04/28/14}} |
Letter Sequence RAI |
|---|
TAC:MF2741, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) TAC:MF2742, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
|
MONTHYEARRA-13-001, Request for Additional Information - Alternate Repair of the Service Water Piping2013-08-30030 August 2013
Request for Additional Information - Alternate Repair of the Service Water Piping
Project stage: Request
ML13247A7012013-08-30030 August 2013
E-mail Relief Request RA-13-001
Project stage: Other
ML13247A7562013-08-31031 August 2013
Verbal Authorization for RR RA-13-001, Temporary Repair of Service Water Piping Seabrook Station August 31, 2013
Project stage: Request
SBK-L-13173, Relief Request RA-13-001, Revision 1, Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii)2013-09-0404 September 2013
Relief Request RA-13-001, Revision 1, Proposed Alternative in Accordance with 10 CFR 50.55a (a)(3)(ii)
Project stage: Request
ML13262A5002013-09-12012 September 2013
License Amendment Request for a Revision to Technical Specification 3.3.2 in Support of NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies.
Project stage: Request
ML13297A1162013-11-0101 November 2013
Acceptance of Requested Licensing Action License Amendment Request for a Revision to Technical Specification 3.3.2 in Support of NRC Order EA-12-049, (TAC Nos. MF2741 and MF2742)
Project stage: Acceptance Review
ML13247A7772014-02-0909 February 2014
Request for Relief to Use an Alternative to the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
Project stage: Acceptance Review
ML14097A1182014-04-0909 April 2014
Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint
Project stage: RAI
ML14114A5262014-04-28028 April 2014
Request for Additional Information Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint
Project stage: RAI
MNS-14-043, (Mns), Units 1 and 2, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Proposed Changes to Technical Specification (TS) 3.3.2, in Support of Compliance with NRC Order EA-12-049.2014-05-20020 May 2014
(Mns), Units 1 and 2, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Proposed Changes to Technical Specification (TS) 3.3.2, in Support of Compliance with NRC Order EA-12-049.
Project stage: Response to RAI
MNS-14-056, Response to Request for Additional Information Regarding License Amendment Request (LAR) for Proposed Changes to Technical Specification (TS) 3.3.2, in Support of Compliance with NRC Order EA-12-049 (TAC Nos. MF2741, 2742)2014-07-22022 July 2014
Response to Request for Additional Information Regarding License Amendment Request (LAR) for Proposed Changes to Technical Specification (TS) 3.3.2, in Support of Compliance with NRC Order EA-12-049 (TAC Nos. MF2741, 2742)
Project stage: Response to RAI
ML14211A4032014-08-27027 August 2014
Issuance of Amendments Regarding Technical Specification 3.3.2 in Support of Compliance with NRC Order EA-12-049
Project stage: Approval
2014-02-09
[Table View] |
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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:Request for Additional Information (RAI)
MONTHYEARML23151A3482023-05-30030 May 2023
Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23142A2732023-05-22022 May 2023
Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)
ML23030B9032023-01-30030 January 2023
Formal Release of RAIs for McGuire Unit 1, Relief Request Impractical RPV Rx Coolant System Welds, Due March 1, 2023 (Email)
ML23017A2232023-01-13013 January 2023
Request for Additional Information (RAI) Issuance for McGuire Unit 1 Steam Generator Tube Inspection Report (Email)
ML22175A0162022-06-24024 June 2022
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
ML22115A1412022-04-25025 April 2022
NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information
ML22102A2962022-04-13013 April 2022
Request for Withholding Information from Public Disclosure Response to Request for Additional Information
ML22063B1782022-03-0909 March 2022
Request for Additional Information Regarding LAR for Revision to the Conditional Exemption of the End of Cycle Moderator Temperature Coefficient Measurement Methodology (EPID L-2021-LLA-0198) NON-PROPRIETARY
ML22010A0732022-01-0606 January 2022
50.59 Inspection Information Request
ML21354A8612021-12-15015 December 2021
NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156)
ML21267A2782021-09-23023 September 2021
50.59 Inspection Information Request
ML21252A0532021-09-0808 September 2021
NRR E-mail Capture - Formal Release of Rais, 30 Day Response, Mcguire Relief Request, Ref: Later Edition Addenda ASME Code, Section XI, 50.55a(g)(4)(iv)
ML21103A0542021-04-13013 April 2021
NRR E-mail Capture - Extension to Request for Additional Information AMS Topical Report AMS-TR-0720R1
ML21067A6742021-03-0505 March 2021
NRR E-mail Capture - Final Request for Additional Information AMS Topical Report AMS-TR-0720R1
ML21049A2632021-02-0404 February 2021
NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan
ML21020A0682021-01-20020 January 2021
Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000369/2021011 and 05000370/2021011) and Request for Information (RFI)
ML20346A0212020-12-10010 December 2020
NRR E-mail Capture - Formal Release of RAIs - License Amendment to Change TS 3.8.1 Due Jan. 29, 2021
ML20323A4072020-11-18018 November 2020
NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180)
ML20216A3512020-08-0303 August 2020
Mcquire U-1 ISI RFI
ML20101L3132020-04-10010 April 2020
Notification of Inspection and Request for Information
ML20071D0962020-03-0505 March 2020
NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station Unit 1 Delay in Update of the Code of Record for in Service Inspections
ML20050D3382020-02-21021 February 2020
Letter RAI 1 MAGNASTOR-Catawba and McGuire Exemptions with Enclosure
ML19354B6372020-01-0707 January 2020
Exemption Request for NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density Request for Additional Information
ML19011A1372019-01-10010 January 2019
NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117)
ML19007A3422018-12-21021 December 2018
NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117)
ML18352A8052018-12-18018 December 2018
NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - MRP-227 Review
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2023-05-30
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 28, 2014 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2: REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION 3.3.2 SETPOINT (TAC NOS. MF2741 AND MF2742)
Dear Mr. Capps:
By letter dated September 12, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML13262A500), Duke Energy Carolinas, LLC (the licensee) submitted a license amendment request, which requested to modify Technical Specification 3.3.2, "Engineered Safety Features Actuation System (ESFAS) Instrumentation." Specifically, the proposed change would modify the setpoint for Auxiliary Feedwater Pump Suction Transfer in support of your efforts to comply with NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events."
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that additional information is needed in order to complete our review. The enclosed document describes this request for additional information (RAI). On April 23, 2014, the Duke staff indicated that a response to the RAI would be provided by May 23, 2014.
If you have any questions, please call me at 301-415-2481.
G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATION 3.3.2 '
IN SUPPORT OF COMPLIANCE WITH NRC ORDER EA-12-049 DOCKET NOS. 50-369 AND 50-370 By letter dated September 12, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13262A500), Duke Energy Carolinas submitted a license amendment request (LAR) to amend the Technical Specifications (TSs) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," FUNCTION 6.f, "Auxiliary Feedwater Pump Suction Transfer on Suction Pressure- Low (c)" for McGuire Nuclear Station, Units 1 and 2, in support of plant modifications required to achieve compliance with the NRC Order EA-12-049, "Order Modifying Licenses with Regard to Requirements of Mitigation Strategies for Beyond-Design-Basis External Events; dated March 12, 2012. In order for the NRC staff to complete its review of the LAR, the following additional information is requested.
- 1. In the submittal, Duke stated:
The existing safety-related automatic alignment of NSW to the AFW p~mps' suction is achieved by means of pressure switches which open AC-motor operated valves. The pressure switches are located on the AFW pump suction lines. The AFW MOPs utilize two pressure switches per train (one switch per isolation valve). The TDAFWP utilizes four switches per train. A low pressure signal sensed by two switches on either train will cause the assured NSW supply of water for the pump to be aligned.
The NRC staff acknowledges that a low pressure signal sensed by two switches on a train of pressure switches associated with the motor-driven auxiliary feedwater pump will open flow from the service water header to the pump's suction. However, the submittal indicated that the turbine-driven auxiliary feedwater pump has four pressure switches per train. From the description given, it appears that there are actually two trains of two switches in this logic, each train associated with a different nuclear service water header.
If this is the situation, the above statement, "A low pressure signal sensed by two switches on either train will cause the assured NSW supply of water for the pump to be aligned," would not be true for all cases for the turbine-driven auxiliary feedwater pump.
In this case, only a select two pressure switches of the four switches will open flow from a service water header.
The NRC staff requests the licensee to clarify its description of the pressure switch logic associated with the turbine-driven* auxiliary feedwater pump and make any necessary changes.
- 2. The licensee is proposing different setpoints for the pressure switches on the "2A" motor-driven auxiliary feedwater pumps. The TSs are combined for Unit 1 and Unit 2.
Enclosure
Figure 1 in Attachment 4 shows some piping configurations are different for the two units, especially where the new "SSS/ELAP" supply of water ties into the suction piping.
The NRC staff requests confirmation that the elevation difference for the "2A" motor-driven auxiliary feedwater pumps is 2-feet on both units.
ML14114A526 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/DSS/SBPB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME GEMiller SFigueroa GCasto RPascarelli GEM iller DATE 04/28/14 04/28/14 04/07/14 04/28/14 04/28/14
