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| Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - IRLT (CACs MF9020 and MF9021; EPID L-2016-LLA-0032) | | Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - IRLT (CACs MF9020 and MF9021; EPID L-2016-LLA-0032) |
| PT, By letter dated December 19, 2016 (Agencywide Documents Access Management System (ADAMS) | | PT, By letter dated December 19, 2016 (Agencywide Documents Access Management System (ADAMS) |
| Accession No. ML16363A349) as supplemented by letter dated May 25, 2017 (ADAMS Accession No. | | Accession No. ML16363A349) as supplemented by letter dated May 25, 2017 (ADAMS Accession No. ML17156A563), Duke Energy, (the licensee), requested changes to the Technical Specifications (TSs) for McGuire Nuclear Station (McGuire), Units 1 and 2. The proposed change would permit the existing Containment 10 CFR 50 Appendix J Type A Integrated Leakage Rate Test (ILRT) intervals to be extended from 10 years to 15 years and the Type C test (LLRT) intervals for qualifying containment isolation valves (CIVs) to be extended from 60 months up to 75 months on a permanent basis. |
| ML17156A563), Duke Energy, (the licensee), requested changes to the Technical Specifications (TSs) for McGuire Nuclear Station (McGuire), Units 1 and 2. The proposed change would permit the existing Containment 10 CFR 50 Appendix J Type A Integrated Leakage Rate Test (ILRT) intervals to be extended from 10 years to 15 years and the Type C test (LLRT) intervals for qualifying containment isolation valves (CIVs) to be extended from 60 months up to 75 months on a permanent basis. | |
| In order to complete its review, the U.S. Nuclear Regulatory Commission staff requests the following additional information. Please provide your response to the following requests for additional information (RAIs) within 30 days of the date of this correspondence. | | In order to complete its review, the U.S. Nuclear Regulatory Commission staff requests the following additional information. Please provide your response to the following requests for additional information (RAIs) within 30 days of the date of this correspondence. |
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Letter Sequence RAI |
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CAC:MF9020, Implement 10 CFR 50, Appendix J, Option B (Approved, Closed) EPID:L-2016-LLA-0032, Implement 10 CFR 50, Appendix J, Option B (Approved, Closed) |
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Category:E-Mail
MONTHYEARML24029A1132024-01-16016 January 2024 Notification of Inspection and Request for Information (Email) 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 ML23192A0552023-07-11011 July 2023 Relief Request Later Edition of ASME Code for ISI ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies 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) ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23087A0282023-03-27027 March 2023 Acceptance of Requested Licensing Action Amendment TSTF-505 ML23087A2492023-03-27027 March 2023 50.69 Acceptance Email ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) 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) ML22291A4602022-10-17017 October 2022 Relief Request Impractical RPV and Rx Coolant Sys. Welds ML22242A1602022-08-30030 August 2022 Hardship Relief Request Pilot-Operated Relief Valve Acceptance Review Results ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22083A0702022-03-24024 March 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, and McGuire Nuclear Station, Units 1 and 2 - Acceptance Review for TSTF-569 LAR ML22049B0152022-02-17017 February 2022 NRC RP Inspection Document Request Letter ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22024A3952022-01-24024 January 2022 Acceptance of Requested Licensing Action Amendment McGuire RCS PT Limits Change TS 3.4.3 and EFPY Changes ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility 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) ML21286A7812021-11-22022 November 2021 Acceptance of Requested Licensing Action Revision to the End of Cycle Moderator Temperature Coefficient Measurement Methodology ML21295A0372021-10-0505 October 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-577 Revised Frequencies for Steam Generator Tube Inspections 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) ML21195A2022021-07-14014 July 2021 NRR E-mail Capture - McGuire Relief Request Acceptance Review Results; McGuire Unit 1 RR, 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 ML21096A3002021-04-0606 April 2021 E-mail for Approval of Proprietary Withholding for Duke Energy Exemptions for the Magnastor Storage Cask ML21096A2512021-04-0505 April 2021 NRR E-mail Capture - McGuire Emergency Plan Submittal, Letter Dated March 31 2021 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 ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML21006A4302021-01-0606 January 2021 Acceptance Review - Duke Fleet RA-20-0207 Request to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation 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) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20216A3512020-08-0303 August 2020 Mcquire U-1 ISI RFI ML20177A3792020-06-23023 June 2020 Email from L. Cox, North Carolina Department of Health and Human Services to NRC Regarding Exemption Request for Duke Energy'S McGuire Nuclear Station ML20140A0852020-05-19019 May 2020 ADAMS 2D 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 ML20029E8592020-01-24024 January 2020 NRR E-mail Capture - McGuire Nuclear Station, Unit 1 -Acceptance of Requested Licensing Action Request to the 10-year ISI Interval Update ML20015A3162020-01-14014 January 2020 1/7/2020, E-Mail from M. Coflin to DCR Approval of Exemption Request McGuire Nuclear Facility ML20008D5592020-01-0707 January 2020 Email to Nc Shpo Exemption Request McGuire Nuclear Facility 2024-01-16
[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 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 ML15289A5852015-10-26026 October 2015 Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System 2023-05-30
[Table view] |
Text
NRR-PMDAPEm Resource From: Mahoney, Michael Sent: Monday, November 13, 2017 12:22 PM To: PT Vu Cc: Jeff Thomas (Jeff.Thomas@duke-energy.com)
Subject:
Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 - IRLT (CACs MF9020 and MF9021; EPID L-2016-LLA-0032)
PT, By letter dated December 19, 2016 (Agencywide Documents Access Management System (ADAMS)
Accession No. ML16363A349) as supplemented by letter dated May 25, 2017 (ADAMS Accession No. ML17156A563), Duke Energy, (the licensee), requested changes to the Technical Specifications (TSs) for McGuire Nuclear Station (McGuire), Units 1 and 2. The proposed change would permit the existing Containment 10 CFR 50 Appendix J Type A Integrated Leakage Rate Test (ILRT) intervals to be extended from 10 years to 15 years and the Type C test (LLRT) intervals for qualifying containment isolation valves (CIVs) to be extended from 60 months up to 75 months on a permanent basis.
In order to complete its review, the U.S. Nuclear Regulatory Commission staff requests the following additional information. Please provide your response to the following requests for additional information (RAIs) within 30 days of the date of this correspondence.
RAI-02
Section 3.1.6.3 on page 16 of Enclosure 1 of the LAR states, The EPRI methodology used to estimate the increase in LERF is conservative. Section 7.0 on page 35 of Attachment 5 of the LAR also states, The EPRI methodology used to estimate the increase in LERF is conservative. Therefore, even though the increase in LERF is near the Regulatory Guide 1.174 threshold, the conservative methodology adds margin.
Section 3.1.6.3 on page 16 of Enclosure 1 and page 36 of Attachment 5 of the LAR both state, Therefore, increasing the ILRT interval to 15 years is considered to be insignificant since it represents a very small change to the MNS risk profile.
Based on the discussion above, address the following:
- a. With the total LERF for both Unit 1 (7.83E-6/yr) and Unit 2 (8.59E-6/yr) being close to the 1E-5/yr threshold, confirm that the conservative methodology made in this ILRT analysis maintain LERF within Region II of RG 1.174. When citing conservatism in the base PRA model, confirm that calculation of the differential risk for the application is also conservative (i.e., the risk estimated for the before versus after condition uses the same assumptions, etc., except for the change to any basic event values affected by the application, ensuring that the before value is not overestimated such that subtracting it from the after value could underestimate the risk increase).
- b. Even if the conservative methodology maintains LERF within Region II of RG 1.174, the change to the MNS risk profile is not considered to be very small, and therefore not insignificant. Justify the reasoning for considering this LAR to be insignificant to the risk profile and to represent a very small change if the LAR is within Region II of RG 1.174.
RAI-03
According to Regulatory Issue Summary 2007-06 the NRC staff expects that licensees fully address all scope elements with Revision 2 of Regulatory Guide (RG) 1.200 by the end of its implementation period (i.e., one 1
year after the issuance of Revision 2 of RG 1.200). Revision 2 of RG 1.200 endorses, with exceptions and clarifications, the combined American Society of Mechanical Engineers (ASME)/American Nuclear Society (ANS) PRA standard (ASME/ANS RA-Sa-2009).
On page 13 of Enclosure 1 of the LAR, the licensee states, The technical adequacy of the MNS PRA is consistent with the guidance of Regulatory Guide 1.200 Revision 2. Given the guidance listed above:
- a. Confirm that the peer reviews of the Internal Flood PRA in September 2011, the LERF PRA in December 2012, and the Internal Events PRA in June 2015, cited on page 37 of Attachment 5 of the LAR were reviewed against the 2009 ASME/ANS PRA Standard, as clarified by RG 1.200, Revision 2.
If not, please identify any gaps between the peer review and the requirements in RG 1.200, Revision 2.
- b. Identify when the peer review of the Fire PRA and the High Winds PRA was performed, and confirm that the peer review of the High Winds PRA, cited on page 37 of Attachment 5 of the LAR was reviewed against the 2009 ASME/ANS PRA Standard, as clarified by RG 1.200, Revision 2. If not, please identify any gaps between the peer review and the requirements in RG 1.200, Revision 2.
RAI-04
For the disposition of F&O WPR A3-1 in Attachment 5 on page 58 of the LAR, the licensee states, Failure of the Main Steam and Feedwater lines due to wind pressure or missile is modeled as failing both diesel generators. As a result, wind pressure fragilities are a major contributor to the MNS plant CDF. Next, the licensee states, The re-evaluation provided a significantly higher wind loading. Incorporating this re-evaluation, along with adding separate failure modes for wind pressure and missiles in to the PRA, reduced the calculated CDF / LERF risk.
Based on the information provided in the disposition, it is unclear how a significantly higher wind loading for the Main Steam and Feedwater lines would reduce CDF and LERF, unless the licensee meant the higher wind loading is actually a higher threshold for withstanding wind loading. It is also unclear how adding separate failure modes would reduce CDF and LERF. Clarify how assuming a higher wind load and how adding separate failure modes for the Main Steam and Feedwater lines reduces the plant CDF and LERF.
RAI-05
For the disposition of F&O SF A5-01, the licensee states, No impact on quantification of Fire PRA or Change Evaluations: seismic-fire interaction is purely qualitative per NUREG/CR-6850.
The NRC agrees there is no quantitative impact on the Fire PRA due to fire-seismic interactions, however this finding is qualitative in nature, and the licensee does not address the qualitative risk from lack of fire brigade training requirements on fire-seismic interactions. Identify how the training requirements in the fire brigade training program addresses fire-seismic interactions. If there is no requirement in the fire brigade training program, identify how the licensees fire brigade is trained to handle fire-seismic interactions. If no such requirement or training exists, evaluate the qualitative impact of fire-seismic interactions on the Fire PRA.
Once this email is added to ADAMS, I will provide the accession number for your reference.
Thanks Mike Michael Mahoney McGuire and Catawba Project Manager, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Desk: (301)-415-3867 Email: Michael.Mahoney@NRC.GOV 2
3 Hearing Identifier: NRR_PMDA Email Number: 3831 Mail Envelope Properties (afd7fc35446c40ec804bab8f1e79fcb2)
Subject:
Request for Additional Information - McGuire Nuclear Station, Units 1 and 2 -
IRLT (CACs MF9020 and MF9021; EPID L-2016-LLA-0032)
Sent Date: 11/13/2017 12:22:23 PM Received Date: 11/13/2017 12:22:25 PM From: Mahoney, Michael Created By: Michael.Mahoney@nrc.gov Recipients:
"Jeff Thomas (Jeff.Thomas@duke-energy.com)" <Jeff.Thomas@duke-energy.com>
Tracking Status: None "PT Vu" <Phong.Vu@duke-energy.com>
Tracking Status: None Post Office: R4PWMSMRS03.nrc.gov Files Size Date & Time MESSAGE 6465 11/13/2017 12:22:25 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: