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MONTHYEARML11279A0352011-09-21021 September 2011 Relief Request Serial # 11-MN-001, Limited Weld Examinations for Refueling Outages 1EOC20 and 2EOC19 Project stage: Request ML12061A2982012-03-0101 March 2012 NRR E-mail Capture - Request for Additional Information for Relief Request 11-MN-001 Submitted September 21, 2011 Project stage: RAI ML12173A0612012-06-0404 June 2012 Relief Request Serial # 11-MN-001, Response to Request for Additional Information on Limited Weld Examinations for Refueling Outages 1 EOC20 and 2EOC19 Project stage: Response to RAI ML12250A4012012-09-13013 September 2012 Proposed Relief Request 11-MN-001 (TAC Nos. ME7268, ME7269, ME7270, ME7271, ME7272, ME7273, and ME7274) Project stage: Other 2012-03-01
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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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NRR-PMDAPEm Resource From: Thompson, Jon Sent: Thursday, March 01, 2012 11:32 AM To: Ashe, Ken; Vu, Phong T Cc: Salgado, Nancy; Widrevitz, Dan; Cumblidge, Stephen; Lupold, Timothy; Rosenberg, Stacey
Subject:
Request for Additional Information for Relief Request 11-MN-001 submitted September 21, 2011
SUBJECT:
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (MCGUIRE 1 AND 2), REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RELIEF REQUEST (RR) 11-MN-001, LIMITED WELD EXAMINATIONS FOR REFUELING OUTAGES 1EOC20 and 2EOC19 (TAC NOS. ME7268 THROUGH ME7274)
By letter dated September 21, 2011, Duke Energy Carolinas, LLC (the licensee), submitted the subject RR for McGuire 1 and 2. The U.S. Nuclear Regulatory Commission staff has reviewed the licensees submittal and determined that an RAI is needed in order to complete our review. The enclosed document describes this RAI. A written response should be provided to the NRC staff for these RAI questions by April 13, 2012, in order to support our timely review of this request. Please inform me as soon as possible if you are unable to support this response timeframe.
If you have any questions, please call me at 301-415-1119.
Sincerely, Jon Thompson, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370
Enclosure:
As stated OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 11-MN-001 LIMITED WELD EXAMINATIONS FOR REFUELING OUTAGES 1EOC20 and 2EOC19 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 By letter dated September 21, 2011, Duke Energy Carolina, LLC (the licensee) submitted Relief Request (RR) 11-MN-001, Limited Weld Examinations for Refueling Outages 1EOC20 and 2EOC19 (Agencywide Documents Access and Management System Accession No. ML11279A035) requesting relief from the weld examination coverage requirements specified in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, 2001 Edition, as amended by Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a (b)(2)(xv)(A)(2), for ten full-penetration welds involving piping due to access limitations caused by design.
The U.S. Nuclear Regulatory Commission (NRC) staff needs the following further information in order to complete its review:
1
For sections 2, 4, 10, 11, 12, 13, 14, 15, 16, and 17:
- 1. To determine the level of safety significance for each weld, NRC staff needs to know which system would be impacted by a leak or failure of the weld or welded attachment in question. This information is provided in the enclosures for some, but not all welds. To assist the NRC staff in assessing each weld, please provide a table for all welds in RR sections 2, 4, 10, 11, 12, 13, 14, 15, 16, and 17 that describes the locations of each weld and the systems to which each weld belongs.
- 2. In sections 2, 4, 10, 11, 12, 13, 14, 15, 16, and 17 the components are described as being made of stainless steel. For each weld, please specify which components, if any, are made of cast stainless steel.
- 3. For sections 10 and 16, specify whether welds of similar compositions have had any history of degradation at McGuire 2. If there has been degradation in similar welds, explain why the subject welds is not vulnerable to the same degradation.
- 4. The difficulties on obtaining coverage in several welds seem to be caused by the use of fixed-angle probes with a limited range available for scanning. Provide a discussion on alternative examination methods and techniques such as phased-array ultrasonic techniques (line scan or raster) that cover many angles that can be used to obtain greater coverage for welds in sections 2, 4, 13, 14, and 15.
For sections 3, 5, 6, 7, 8, and 9:
- 5. No actual alternatives are specified under the Proposed Alternative and Basis for Use. Specify the requested alternative and basis for use for all sections.
- 6. Specify whether any indications, acceptable or otherwise, were detected during the examinations.
For section 3:
- 7. Specify material compositions of the weld and adjoining materials. Was the stainless steel cast?
- 8. Specify whether welds of similar composition (carbon steel to stainless steel of the same types) have any history of degradation at McGuire 1. Explain why the subject weld is, or is Not, vulnerable to the same degradation.
For section 9:
- 9. Specify the number of similar welds in the system, and the coverage percentages for these should they have been tested as part of the third In-service inspection (ISI) program.
- 10. Justify how the examined volume can provide assurance regarding the condition of the entire weld-length:
- a. What has been the operating experience for these welds? Have indications been found in similar welds? Have similar welds required repair/mitigation?
- b. What would the consequences of these welds failing be? Would the consequences be safety significant, or impact safety systems?
Enclosure 2
Hearing Identifier: NRR_PMDA Email Number: 282 Mail Envelope Properties (Jon.Thompson@nrc.gov20120301113100)
Subject:
Request for Additional Information for Relief Request 11-MN-001 submitted September 21, 2011 Sent Date: 3/1/2012 11:31:40 AM Received Date: 3/1/2012 11:31:00 AM From: Thompson, Jon Created By: Jon.Thompson@nrc.gov Recipients:
"Salgado, Nancy" <Nancy.Salgado@nrc.gov>
Tracking Status: None "Widrevitz, Dan" <Dan.Widrevitz@nrc.gov>
Tracking Status: None "Cumblidge, Stephen" <Stephen.Cumblidge@nrc.gov>
Tracking Status: None "Lupold, Timothy" <Timothy.Lupold@nrc.gov>
Tracking Status: None "Rosenberg, Stacey" <Stacey.Rosenberg@nrc.gov>
Tracking Status: None "Ashe, Ken" <Ken.Ashe@duke-energy.com>
Tracking Status: None "Vu, Phong T" <Phong.Vu@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 5051 3/1/2012 11:31:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: