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Category:E-Mail
MONTHYEARML24207A0862024-07-24024 July 2024 Relief Request Acceptance Review Results - McGuire Units 1 and 2 Alternatives Component Cooling Pumps, RHR Pumps ML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24033A2372024-02-0202 February 2024 Acceptance of Requested Licensing Action Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations (Epids L-2024-LLR-0002 and L-2024-LLR-0003) ML24029A1132024-01-16016 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) ML23087A2492023-03-27027 March 2023 50.69 Acceptance Email ML23087A0282023-03-27027 March 2023 Acceptance of Requested Licensing Action Amendment TSTF-505 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 2024-07-24
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1 NRR-PMDAPEm Resource From: Miller, Ed Sent: Tuesday, June 10, 2014 11:02 AM To: 'Vu, Phong T (Phong.Vu@duke-energy.com)'
Subject:
Draft RAI for Relief Request 13-MN-003 Attachments:Draft EPNB RAI.docx PT, The NRC staff's draft RAI for the subject relief request is atta ched to this e-mail. The draft RAI is not an official NRC staff request and is being provided to you to facilitate a subsequent conference call to determine: 1) If the questions clearly convey the NRC staff information needs; 2) Whether the regulatory basis for the questions is understood; 3) Whether the information is already available in existing, docketed, correspondence; and 4) To determine an appropriate response time-frame. After you've had a chance to review the draft information request, please contact me to schedule the conference call.
Ed Miller
(301) 415-2481
Hearing Identifier: NRR_PMDA Email Number: 1352 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CAFD0D8A321D)
Subject:
Draft RAI for Relief Request 13-MN-003 Sent Date: 6/10/2014 11:02:20 AM Received Date: 6/10/2014 11:02:00 AM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients: "'Vu, Phong T (Phong.Vu@duke-energy.com)'" <Phong.Vu@duke-energy.com> Tracking Status: None
Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 669 6/10/2014 11:02:00 AM Draft EPNB RAI.docx 27397 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
DRAFT REQUEST FOR ADDITIONAL INFORMATION MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 THIRD 10-YEAR INSERVICE INSPECTION INTERVAL RELIEF REQUEST NO. 13-MN-003 DOCKET NOS. 50-369 AND 50-370
By letter dated February 6, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14055A402), Duke Energy Carolinas (Duke) submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for relief from certain requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for the third 10-year Inservice Inspection (ISI) Program for McGuire Nuclear Station, Unit 2 (McGuire 2). In order for the NRC staff to complete its review of the relief request, the following additional
information is requested.
- 1. What is the normal operating temperature and pressure for the subject welds (2ELDHX-HD-FLG & 2RCHPSS-OUT-1).
- 2. What environmental conditions are the subject welds, (2ELDHX-HD-FLG & 2RCHPSS-OUT-1), exposed to (e.g., system transients, vibration, flow)?
- 3. Describe the materials of construction for the stainless steel head, weld metal, and carbon steel flange in weld 2ELDHX-HD-FLG.
- 4. Describe the weld metal used in 2RCHPSS-OUT-1.
- 5. Has Duke performed a review of applicable operating experience for the subject welds? If so, did this review identify any industry operating experience of similar system welds developing service induced cracking or failure?