Letter Sequence Response to RAI |
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TAC:MF2741, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) TAC:MF2742, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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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
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Category:Letter
MONTHYEARML24311A1882024-11-0808 November 2024 Request to Remove Document from Public Availability and Withhold Proprietary Information from Public Disclosure, Mcguire Nuclear Station, Unit No. 1 ML24304A9602024-11-0505 November 2024 Proposed Alternative for the Inspection of Reactor Vessel Closure Head Penetrations IR 05000369/20240032024-11-0404 November 2024 Integrated Inspection Report 05000369/2024003 and 05000370/2024003 ML24303A4212024-10-30030 October 2024 Mcguire Nuclear Station, Units 1 & 2, Notification of an NRC Fire Protection Team Inspection FPTI NRC 05000369/2025010, 05000370/2025010 and Request for Information RFI IR 05000369/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 05000369/LER-1923-001, Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error2023-12-13013 December 2023 Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230032023-10-24024 October 2023 Integrated Inspection Report 05000369/2023003 and 05000370/2023003; and Inspection Report 07200038/2023001 IR 05000369/20230102023-10-13013 October 2023 Age Related Degradation Inspection Report 05000369/2023010 and 05000370/2023010 IR 05000369/20240102023-10-13013 October 2023 Notification of McGuire Nuclear Station Comprehensive Engineering Team Inspection – U.S. Nuclear Regulatory Commission Inspection Report 05000369, 370/2024010 ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds IR 05000369/20233012023-09-20020 September 2023 William B. McGuire Nuclear Station - NRC Examination Report 05000369/2023301 and 05000370/2023301 ML23230A0652023-08-31031 August 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Relief Request Use of Later Edition of ASME Code ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000369/20230052023-08-25025 August 2023 Updated Inspection Plan for McGuire Nuclear Station Units 1 and 2 (Report 05000369/2023005 and 05000370/2023005) IR 05000369/20234012023-08-0404 August 2023 – Security Baseline Inspection Report 05000369/2023401 and 05000370/2023401 (OUO-SRI) Cover IR 05000369/20230022023-07-28028 July 2023 Integrated Inspection Report 05000369/2023002 and 05000370/2023002 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 ML23115A2122023-05-0101 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report IR 05000369/20230012023-05-0101 May 2023 Integrated Inspection Report 05000369/2023001 and 05000370/2023001 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 Enclosurequest for Additional Information (Letter to A. Zaremba Request for Additional Information for Review of Duke Energy'S Decommissioning Funding Plan Update) ML17331B1492017-11-21021 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Nsws One-Time LAR (CACs MG0242 and MG0243, EPID L-2017-LLA-0299) ML17317B0932017-11-13013 November 2017 NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - Irlt (CACs MF9020 and MF9021; EPID L-2016-LLA-0032) ML17230A1512017-08-15015 August 2017 Notification of Inspection of Inspection and Request for Information ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17135A0322017-05-12012 May 2017 NRR E-mail Capture - Request for Additional Information - McGuire TSTF-197 ML17114A4992017-04-17017 April 2017 Emergency Preparedness Inspection and Request for Information ML16302A1122016-11-0404 November 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program (CAC Nos. MF2934 and MF2935) MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program2016-09-29029 September 2016 Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program ML16228A2612016-08-15015 August 2016 Email - McGuire Unit No. 1: Request for Additional Informati- Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping. ML16194A2862016-07-12012 July 2016 E-Mail - Mcguirai Ice Condenser Door Position Alternate Verification, (ML16089A228) CAC Nos. MF7526 and MF7527 ML16175A0222016-07-12012 July 2016 Request for Additional Information Regarding License Amendment Request to Implement a Risk-Informed, Performance-Based Fire Protection Program ML16014A6882016-01-20020 January 2016 Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Scheme ML15348A2602015-12-17017 December 2015 Request for Additional Information Regarding License Amendment Request to Use an Alternative Fission Gas Gap Release Fraction ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15289A5552015-10-26026 October 2015 Request for Additional Information Regarding License Amendment Request Nuclear Service Water System Allowed Outage Time Extension 2024-07-15
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Steven D. Capps Vice President DUKE McGuire Nuclear Station ENERGY. Duke Energy MG01VP 112700 Hagers Ferry Road Huntersville, NC 27078 o: 980-875-4805 f: 980-875-4809 Steven.Capps@duke-energy.com July 22, 2014 Serial: MNS-14-056 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
SUBJECT:
Duke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station (MNS), Units 1 and 2 Docket Nos. 50-369 and 50-370 Renewed License Nos. NPF-9 and NPF-17 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-1 2-049 (TAC Nos. MF 2741, 2742)
REFERENCES:
- 1. Letter dated September 12, 2013 from Duke Energy to NRC, 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 for Beyond-Design-Basis External Events", dated March 12, 2012 (Adams Accession No.) ML13262A500
- 2. Letter dated April 9, 2014 from NRC to Duke Energy, "Request for Additional Information" Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint.
ML14097A1 18 3. Letter dated April 28, 2014 from NRC to Duke Energy, "Request for Additional Information" Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint.
ML14114A526
- 4. Letter dated May 20, 2014 from Duke Energy to NRC, "Response to Request for Additional Information for Proposed Changes to Technical Specification 3.3.2, in Support of Compliance with NRC Order EA-12-049 (TAC Nos. MF 2741, 2742)5. Letter dated July 14, 2014 from NRC to Duke Energy, "Request for Additional Information" Regarding License Amendment Request to Modify Technical Specification 3.3.2 Setpoint.
ML14178B232 U.S. Nuclear Regulatory Commission July, 22, 2014 Page 2 In Reference 1, Duke Energy submitted a LAR for a revision to TS 3.3.2 in support of NRC Order EA-12-049.
In References 2, 3, and 5 the NRC transmitted Requests for Additional Information (RAIs)regarding the LAR. Reference 4 provided the response to References 2 and 3.The purpose of this letter is to respond to the Reference 5 RAI letter questions.
The enclosures to this letter constitute McGuire's response.
In Enclosure 1 the format for each RAI response is to restate the RAI question, followed by the appropriate response.
Enclosure 2 is included to provide the requested calculation attachment supporting the information documented in Reference 1 and 5.There are no regulatory commitments contained in this letter or its attachments.
If you have any questions or require additional information, please contact George Murphy at (980) 875-5715.I declare under the penalty of perjury that the foregoing is true and correct.Executed on July 22, 2014.Sincerely, Steven D. Capps ENCLOSURES
- 1. Reference 5 RAI Questions and Responses 2. Attachment 6 of MCC-1210.04-00-0043, Revision 5, Instrument Uncertainty for CA-RN Swapover Suction Pressure Switch Loops U.S. Nuclear Regulatory Commission July, 22, 2014 Page 3 xc: V.M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 E.J. Leeds, Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 0-8C2A 11555 Rockville Pike Rockville, MD 20852-2738 G.E. Miller, Project Manager (MNS and CNS)U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station J. Folkwein American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4453 ENCLOSURE 1 Reference 5 RAI Questions and Responses Page 2 of 5 ENCLOSURE 1 REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 PROPOSED CHANGES TO TECHNICAL SPECIFICATION
3.3.2 AUXILIARY
FEEDWATER PUMP SUCTION TRANSFER SETPOINT 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 (Duke) 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. By letter dated April 9, 2014 (ADAMS Accession No.ML1 4097A1 18), the U.S. Nuclear Regulatory Commission (NRC) staff issued a request for additional information (RAI) to Duke. On May 20, 2014 (ADAMS Accession No. ML14161A231), Duke provided a response to the RAI.Additionally, and to support the NRC staff review of the LAR, Duke made supporting documentation for this LAR available via an online reference portal. The purpose of the online reference portal was to allow the NRC staff limited access to the supporting documentation to identify those documents, or portions thereof, that need to be docketed to support the NRC staff's evaluation of the LAR. Upon review of the LAR, the May 20, 2014, response, and the online reference portal, the NRC staff has identified the following informational needs: RAI #1: Please provide the calculation MCC-1210.04.00.0043 that was generated in support of this LAR.RAI #1 Response: Attachment 2 provides the applicable portion of the Auxiliary Feedwater (AFW) suction pressure switch set-point and uncertainty calculation.
Only Attachment 6 and supporting attachments of the calculation were provided, as it represents the future modified plant configuration for the LAR implementation.
The calculation utilized the set-point/uncertainty methodology described in Reference
- 1.
Page 3 of 5 ENCLOSURE 1 RAI #2: In addition to providing the calculation, please clarify the following:
- a. Calculation MCC-1210.04-00-0043 states (see.Calc.
Attachment 6, page No.8 of 11) on PDF page 61 of 64 that both the "Reference Accuracy (A)" and "Calibration Tolerance (C TE)" is 1.0% of span (0.15 psig) with "press (pressure) switch adjustable range from I to 16 psig." On the following page, page 61 of 64, the "As-Left Tolerance (ALT)" is specified as 1.03% span (0.16 psig) for "TSTF-493 AF & AL Tolerances for Technical Specifications Pressure Switches." i. Please explain why the ALT specified in PDF page 61 of 64 is not implemented in the calibration procedure (as described in the paragraph.
quoted below).PDF pages 14 & 15 of 64 (Calc. page Nos. 7 & 8) of the document state: "SRA- Sensor Reference Accuracy -Random, Independent term. The vendor states the reference accuracy as +/-1% of the maximum span (Reference J).However, the'as-left setting band in the calibration procedure is +/- 0.3 psig or +/-2.67% of calibrated span. Since the methodology of calibrating verifies all attributes of the reference accuracy (Assumption G), the larger value for the calibration tolerance may be substituted for reference accuracy as opposed to inclusion of the calibration tolerance as a separate term (Reference 1), The calibration tolerance (as-left setting band) is simply the term used to represent reference accuracy and does not represent a separate uncertainty term.= +/- 2.67% of calibration span." ii. How was the ,+2.67% value determined iii. Please provide justifications how the as-left setting band in the calibration procedure of +/- 2.67% of calibration span will ensure the early detection of instrument channel degradation, compared to reference accuracy band of +/- 1%provided by the vendor, and calculated by the licensee.iv. Please explain how the calculated ALT (see page 62 of 64) is used.v. Please explain how the calculated AFT (see PDF page 62 of 64) is used.b. PDF page 15 of 64 (Calc. Page No. 8) states: "SD -Sensor Drift-A drift study (Attachment
- 5) has been performed on the safety related pressure switches in the CA/RN suction pressure function at McGuire...
This was performed to show that the drift values provided by the vendor is acceptable to the McGuire actual in-use experience.
A 95/95 confidence interval was applied and showed that, +2.67% of calibrated span is conservative relative to actual experience....
= + 2.67% of calibration span."
Page 4 of 5 ENCLOSURE 1 PDF page 16 of 64 (Calc. Page No. 9) shows that the 2.67% value is used to calculate the term "ePS". PDF page 19 of 64 (CaIc. Page No. 12) shows term "eps "Used to calculate TLA calculation.
Therefore the 2.67% value is used to determine TLA in page 18 of 64 (Calc. Page No. 12).i. Please provide details of the analysis performed on plant drift data including the analysis performed on outlier rejection, normality testing, linearity, and 95/95 confidence level.ii. Please explain why the actual plant drift study data is not used in selection of the sensor drift band.c. PDF page 61 of 64 (Calc. Attachment 6, page 8 of 11) states drift (D) as 3.42% of span.This 3.42% drift value is used in the AFT calculation.
PDF page 62 of 64 (Calc. Attachment 6, page 9 of 11) states sensor drift (SO) as 2.67% of span. This drift value is used in TLA calculation in PDF page 15 of 64 (Calc. page 8 of 16) for TLA calculation.
Please explain why sensor drift value of 3.42% is used in AFT calculation and a drift value of 2.67% is used in TLA calculation.
ii. The drift value used for in the AFT is larger than the drift value used in the TLA;therefore the AFT value does not confirm that the drift value used in the TLU calculation is still valid, as it should. Please explain iii. It is assumed that the item referred to as TLA in the body of the calculation is referred to as TLU in Attachment
- 6. Correct?
Page 5 of 5 ENCLOSURE 1 RAI #2 Response: The engineering changes to support the proposed LAR include the replacement of existing Emergency Safety Feature Actuation System (ESFAS) AFW pump suction pressure switches with a different model switch. A different model switch with a wider calibration range is required to accommodate the increased switch calibration set-point.
References
- 1) and 4)previously discussed installation of new pressure switches for the AC independent AFW pump automatic suction transfer feature; however, the replacement of the existing ESFAS AFW pump suction pressure switches was not clearly highlighted.
An informal copy of the entire Auxiliary Feedwater (AFW) suction pressure switch set-point and uncertainty calculation was previously provided to the NRC on the Electronic Share Portal.The calculation body addresses the setpoint/uncertainty determination for the current plant configuration, whereas Attachment 6 of the calculation supports the future LAR plant configuration.
The questions posed within RAI #2 resulted due to apparent discrepancies between the body of the calculation and Attachment 6 of the calculation.
Response to each sub-question within RAI #2 is provided below.Response to RAI #2a) i, ii, iii: Refer to RAI #2 introductory discussion, no further response required.Response to RAI #2a) iv, v (Regarding how the TSTF-493 ALT and AFT will be applied): An example calibration procedure was previously provided in response to Reference
- 2) RAI #2, which depicted a representative calibration procedure example for implementation of TSTF-493 as-found and as-left calibration requirements.
As stated in the prior RAI response (Reference 4), similar calibration procedure changes will be implemented for the AFW pump suction pressure switches addressed by Technical Specification Table 3.3.2-1. In addition to the incorporation of the TSTF-493 as-found and as-left tolerance requirements, the procedure changes will further incorporate requirements for formal evaluation (within the Corrective Action Program) of any instrument channel which could not satisfy the required tolerances.
The changes to the AFW pump suction pressure switch calibration procedure will be implemented as part of the engineering change process.Response to RAI #2b) i, ii: Refer to RAI #2 introductory discussion, no further response required.Response to RAI #2c) i, ii, iii: Refer to RAI #2 introductory discussion, no further response required.