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| | number = ML14097A118 | | | number = ML14097A118 |
| | issue date = 04/09/2014 | | | issue date = 04/09/2014 |
| | 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 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, o,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 9, 2014 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, o,c. 20555-0001 April 9, 2014 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985 |
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| ==SUBJECT:== | | ==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) |
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| 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:== |
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| |
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| ==Dear Mr. Capps:==
| | By letter dated September 12, 2013~(Agencywide Documents Access and Management System (ADAMS) Accession Number ML13262A500), Duke Energy Carolinas, LLC (the licens*ee) 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." |
| By letter dated September 12, Documents Access and Management System (ADAMS) Accession Number ML 13262A500), | | The U.S. Nuclear Regulatory Commission 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 March 31, 2014, the Duke staff indicated that a response to the RAI would be provided by May 23, 2014. |
| Duke Energy Carolinas, LLC (the licens*ee) submitted a license amendment | | If you have any questions, please call me at 301-415-2481. |
| : request, which requested to modify Technical Specification 3.3.2, "Engineered Safety Features Actuation System (ESFAS) Instrumentation."
| | 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 |
| 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 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 March 31, 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 | |
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| ==Enclosure:== | | ==Enclosure:== |
| | Request for Additional Information cc w/encl: Distribution via Listserv |
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| 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 DRAFT REQUEST F0R ADDITIONAL INFORMATION
| | DRAFT REQUEST F0R 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 (TS) 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. |
| ' 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),
| | : 1. Provide an overall summary of calculations performed including the various tolerances used in calculating the total loop uncertainties, reference accuracy, and drift indicating how they comply with applicable requirements of this request (e.g., General Design Criterion (GDC) 13, GDC 20, and 10 CFR 50.36(c)(1 )(ii)(a)). Please ensure that the summary indicates how all these tolerances comply with the 95/95 confidence level specified in RG 1.1 05. |
| Duke Energy Carolinas submitted a license amendment request (LAR) to amend the Technical Specifications (TS) 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," | | : 2. Provide representative plant procedures to demonstrate how the plant procedures comply with the TSTF-493 footnotes. |
| 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," | | Enclosure |
| dated March 12, 2012. In order for the NRC staff to complete its review of the LAR, the following additional information is requested. | |
| : 1. Provide an overall summary of calculations performed including the various tolerances used in calculating the total loop uncertainties, reference | |
| : accuracy, and drift indicating how they comply with applicable requirements of this request (e.g., General Design Criterion (GDC) 13, GDC 20, and 10 CFR 50.36(c)(1
| |
| )(ii)(a)). | |
| Please ensure that the summary indicates how all these tolerances comply with the 95/95 confidence level specified in RG 1.1 05. 2. Provide representative plant procedures to demonstrate how the plant procedures comply with the TSTF-493 footnotes. | |
| Enclosure Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078-8985 | |
| . April 9, 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 (TAG 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 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 March 31, 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.
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| Sincerely,
| |
| /RAJ 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:==
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| Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
| | ML14097A118 OFFICE NRR/LPL2-1 /PM NRR/LPL2-1 /LA NRR/DE/EICB/BC N R RILPL2-1 /BC NAME GEMiller SFigueroa JThorp RPascarelli DATE 04/08/14 04/07/14 04/08/14 04/09/14}} |
| Public RidsAcrsAcnw_MaiiCTR Resource RidsNrrDeEicb Resource RidsNrrLASFigueroa Resource LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsNrrPMMcGuireResource (hard copy) RidsRgn2MaiiCenter Resource ADAMS Accession No ML14097A118 OFFICE NRR/LPL2-1
| |
| /PM NRR/LPL2-1 | |
| /LA NRR/DE/EICB/BC NAME GEMiller SFigueroa JThorp DATE 04/08/14 04/07/14 04/08/14 OFFICIAL RECORD COPY N R RILPL2-1 | |
| /BC RPascarelli 04/09/14}}
| |
Letter Sequence RAI |
|---|
TAC:ME2741, (Withdrawn, Closed) TAC:MF2741, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) TAC:MF2742, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
|
MONTHYEARML1013702032010-05-18018 May 2010
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Project stage: Other
ML1020804472010-08-0404 August 2010
Withdrawal of License Amendment Request Regarding Cyber Security Plan
Project stage: Withdrawal
RA-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
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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
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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
2013-09-04
[Table View] |
|
|---|
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 05000369/20240102023-10-13013 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 05000369/20234012023-08-0404 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
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
ML23124A0862023-05-0303 May 2023
Cycle 29, Revision 1, Core Operating Limits Report (COLR)
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
ML23115A2122023-05-0101 May 2023
Review of the Spring 2022 Steam Generator Tube Inspection Report
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:Request for Additional Information (RAI)
MONTHYEARML24197A1702024-07-15015 July 2024
Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations
ML23151A3482023-05-30030 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
ML18306A9372018-11-0202 November 2018
NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Esps LAR
ML18285A0812018-10-11011 October 2018
NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR
RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018
Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools
ML18138A4662018-05-18018 May 2018
NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - TORMIS LAR
ML18088B2822018-03-29029 March 2018
Requalification Program Inspection - McGuire Nuclear Station
ML18057A2182018-02-23023 February 2018
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2024-07-15
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, o,c. 20555-0001 April 9, 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 licens*ee) 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 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 March 31, 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
DRAFT REQUEST F0R 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 (TS) 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. Provide an overall summary of calculations performed including the various tolerances used in calculating the total loop uncertainties, reference accuracy, and drift indicating how they comply with applicable requirements of this request (e.g., General Design Criterion (GDC) 13, GDC 20, and 10 CFR 50.36(c)(1 )(ii)(a)). Please ensure that the summary indicates how all these tolerances comply with the 95/95 confidence level specified in RG 1.1 05.
- 2. Provide representative plant procedures to demonstrate how the plant procedures comply with the TSTF-493 footnotes.
Enclosure
ML14097A118 OFFICE NRR/LPL2-1 /PM NRR/LPL2-1 /LA NRR/DE/EICB/BC N R RILPL2-1 /BC NAME GEMiller SFigueroa JThorp RPascarelli DATE 04/08/14 04/07/14 04/08/14 04/09/14
