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Category:E-Mail
MONTHYEARML23271A1792023-09-28028 September 2023 Request for Confirmation License Amendment Application to Revise Control Room Cooling TS 3.7.11 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 ML23188A0732023-07-0707 July 2023 Acceptance of Requested Licensing Action License Amendment Application to Revise Control Room Cooling Technical Specifications 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) ML23080A1892023-03-20020 March 2023 RP Inspection Document Request 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) ML22336A0692022-11-28028 November 2022 Final 2023 Catawba Nuclear Station (CNS) Commercial Grade Dedication (CGD) Inspection Information Request ML22303A0052022-10-24024 October 2022 EN 56178 - Tioga Final. LTR-TP-22-29 2021 10CFR Part 21 Improper Notification of NRC NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22213A0472022-08-0101 August 2022 Document Request for Catawba Nuclear Station - Radiation Protection Inspection - Inspection Report 2022-03 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22154A1312022-06-0303 June 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2 - Request for Additional Information Environmentally-Assisted Fatigue License Renewal Commitment ML22174A0802022-06-0101 June 2022 Transmittal External Distribution Notification TR-NUC-CN-014344 - SLC Manual Revision to Loes and SLC 16.7-5 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 ML22041A5312022-02-10010 February 2022 NRR E-mail Capture - Catawba Nuclear Station Unit 2 - Acceptance of Requested Licensing Action Use of Alternative Requirements of ASME Code for Embedded Flaw Repair Method on Reactor Vessel Closure Head Penetration 74 EPID L-2022-LLR-0010 ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22024A1112022-01-0707 January 2022 E-mail Capture- Catawba POV Inspection Information Request (1) 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) ML21335A2252021-12-0101 December 2021 NRR E-mail Capture - Catawba Nuclear Station, Unit 2 - Request for Additional Information Spring 2021 Steam Generator Tube Inspection Report (L-2021-LRO-0043) 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 ML21189A2502021-07-0202 July 2021 NRR E-mail Capture - Acceptance Review: Duke Energy - Proposed Alternative to Use ASME Code Case N-885 for Catawba Nuclear Station Unit 2 - EPID: L-2021-LLR-0043 ML21117A1292021-04-26026 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request RA-21-0145 ML21117A1222021-04-23023 April 2021 NRR E-mail Capture - (External_Sender) Catawba Nuclear Station Relief Request RA-21-0133 ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21099A0742021-04-0909 April 2021 CAT_2021-02 Document Request for Upcoming RP Inspection ML21096A3002021-04-0606 April 2021 E-mail for Approval of Proprietary Withholding for Duke Energy Exemptions for the Magnastor Storage Cask ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 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 ML20338A3932020-12-0303 December 2020 Notification of Inspection and Request for Information 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) ML20260H4622020-09-0909 September 2020 NRR E-mail Capture - Acceptance Review for Mcguire/Catawba EDG Maximum Voltage TS Limit L-2019-014, NRR E-mail Capture - (External Sender) Request for State Comments - Regarding Proposed Amendment to Revise the Catawba, Unit 1, Technical Specification (TS) 3.4.3, RCS Pressure and Temperature (P/T) Limits - State Response2020-07-0707 July 2020 NRR E-mail Capture - (External_Sender) Request for State Comments - Regarding Proposed Amendment to Revise the Catawba, Unit 1, Technical Specification (TS) 3.4.3, RCS Pressure and Temperature (P/T) Limits - State Response ML20191A0242020-07-0707 July 2020 NRR E-mail Capture - Request for State Comments - Regarding Proposed Amendment to Revise the Catawba, Unit 1, Technical Specification (TS) 3.4.3, RCS Pressure and Temperature (P/T) Limits - Staff Solicitation 2023-09-28
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Text
From: Cotton, Karen Sent: Monday, April 26, 2021 9:03 AM To: Zaremba, Arthur H.
Subject:
Catawba Verbal Relief Request RA-21-0145 Attachments: Catawba Verbal Script PA RA-21-0145.pdf Mr. Zaremba:
In accordance with NRR Office Instruction LIC-102, Relief Request Reviews, the NRR staff has provided verbal authorization for Catawba, Unit 2, relief request Proposed Alternative RA-21-0145 as described in your letter to NRC dated April 23, 2021, as supplemented by letter dated April 24, 2021.
Attached is the script for the verbal authorization of relief request Proposed Alternative RA-21-0145 that was provided at approximately 7:00pm EDT on 4/24/2021, by Matthew Mitchell and Michael Markley. The NRC staff intends to follow-up this verbal authorization with a written safety evaluation within approximately 150 days. Please let me know if you have any questions. A copy of this email and verbal authorization will be made publicly available in ADAMS.
- Best, Karen Cotton, Project Manager Catawba NRR/DORL/LPL2-1
Hearing Identifier: NRR_DRMA Email Number: 1147 Mail Envelope Properties (MN2PR09MB5498DD30AAB94E2EE6DC232185429)
Subject:
Catawba Verbal Relief Request RA-21-0145 Sent Date: 4/26/2021 9:02:42 AM Received Date: 4/26/2021 9:02:42 AM From: Cotton, Karen Created By: Karen.Cotton@nrc.gov Recipients:
"Zaremba, Arthur H." <Arthur.Zaremba@duke-energy.com>
Tracking Status: None Post Office: MN2PR09MB5498.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 838 4/26/2021 9:02:42 AM Catawba Verbal Script PA RA-21-0145.pdf 91335 Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
VERBAL AUTHORIZATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FOR PROPOSED ALTERNATIVE RA-21-0145 ALTERNATE REPAIR OF A REACTOR VESSEL HEAD PENETRATION 74 DUKE ENERGY CAROLINAS, LLC CATAWBA UNIT 2 DOCKET NO. 50-414 APRIL 24, 2021 Technical Evaluation Read by Matthew Mitchell, Branch Chief, Piping and Head Penetration Branch, Division of New and Renewed Licenses, Office of Nuclear Reactor Regulation By letter dated April 23, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21113A215) as supplemented by letter dated April 24, 2021 (ADAMS Accession No. ML21114A000), Duke Energy Carolinas, LLC (the licensee) submitted Proposed Alternative RA-21-0145 for the repair of degraded reactor vessel head penetration number 74 at Catawba Nuclear Station, Unit 2 (CNS2). In order to repair the degraded penetration J-groove weld, the licensee proposed to use the embedded flaw repair process described in the NRC-approved WCAP-15987-P, Revision 2-P-A report, with some modifications.
The licensee made this request in accordance with 10 CFR 50.55a(z)(1) on the basis that the proposed alternative repair will provide an acceptable level of quality and safety. The licensee requested the alternative for one cycle of operation.
The NRC staff reviewed the following information: (1) proposed repair method and inspections:
(2) flaw evaluation including a conservatively postulated flaw in the nozzle J-groove weld and potential fatigue crack growth into the reactor vessel head; (3) corrosion resistance of repair weld material (Alloy 52/52M) exposed to reactor coolant; and (4) consistency of the repair, inspection and flaw evaluation methods with those described in the NRC-approved WCAP-15987-P, Revision 2-P-A report and current NRC regulations under 10 CFR 50.55a(g)(6)(ii)(D).
The NRC staff finds that the licensees repair, inspection and flaw evaluation methods are consistent with the guidance in the NRC-approved WCAP-15987-P, Revision-2-P-A report and the inspection requirements specified in ASME Code Case N-729-6, as conditioned in 10 CFR 50.55a(g)(6)(ii)(D). The NRC staff determines that the proposed repair will restore the primary system pressure boundary and provide reasonable assurance that the structural integrity of the reactor vessel head and repaired penetration number 74 for one cycle of operation as requested in the licensees proposed alternative. Therefore, the NRC staff concludes the licensees proposed alternative provides an acceptable level of quality and safety.
NRC Staff Conclusion Read by Michael Markley, Chief of Plant Licensing Branch II-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation As Chief of Plant Licensing Branch II-1, I concur with the Piping and Head Penetration Branchs determinations.
The NRC staff concludes that Proposed Alternative RA-21-0145 will provide an acceptable level of quality and safety for the reactor vessel head and repaired penetration number 74.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the
regulatory requirements set forth in 10 CFR 50.55a(z)(1) and is in compliance with the requirements of the ASME Code,Section XI, ASME Code Case N-729-6 as mandated and conditioned in 10 CFR 50.55a(g)(6)(ii)(D). Therefore, as of April 24, 2021, the NRC authorizes Proposed Alternative RA-21-0145 for one cycle of operation at CNS2 until the end of Cycle 25 that is scheduled to end in fall 2022.
All other requirements of ASME Code,Section XI and 10 CFR 50.55a(g)(6)(ii)(D), for which relief was not specifically requested and authorized by the NRC staff, remain applicable including the third-party review by the Authorized Nuclear Inservice Inspector.
This verbal authorization does not preclude the NRC staff from asking additional questions and clarifications regarding the licensees proposed alternative while preparing the subsequent written safety evaluation.