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Category:E-Mail
MONTHYEARML24197A1702024-07-15015 July 2024 Request for Additional Information Two Proposed Alternatives (RA-23-0242) for the Inspection of Reactor Vessel Closure Head Penetrations ML24192A3492024-07-10010 July 2024 Acceptance of Requested Licensing Action License Amendment Application to Revise Technical Specification 3.4.3, RCS Pressure and Temperature Limits ML24179A1292024-06-24024 June 2024 Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 ML24150A1662024-05-29029 May 2024 Document Request for Catawba Nuclear Station Units 1 & 2 - Radiation Protection Inspection - Inspection Report 2024-03 ML24066A0142024-03-0505 March 2024 Cat 2024-002 Radiation Safety Baseline Inspection Information Request 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) ML23271A1792023-09-28028 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 ML21117A1232021-04-23023 April 2021 NRR E-mail Capture - Catawba Verbal Relief Request Request for Additional Information ML21117A1222021-04-23023 April 2021 NRR E-mail Capture - (External_Sender) Catawba Nuclear Station Relief Request RA-21-0133 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) 2024-07-15
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NRR-PMDAPEm Resource From: Miller, Ed Sent: Monday, July 07, 2014 2:30 PM To: 'lawrence.rudy@duke-energy.com'
Subject:
Draft RAI for Catawba RR 14-CN-001 Attachments: DRAFT Catawba 1-2 RR 14-CN-001 RAI.docx
- Larry, The NRC staffs draft RAI for the subject relief request is attached 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 youve had a chance to review the draft information request, please contact me to schedule the conference call.
Ed Miller (301) 415-2481 1
Hearing Identifier: NRR_PMDA Email Number: 1413 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CAFD30068935)
Subject:
Draft RAI for Catawba RR 14-CN-001 Sent Date: 7/7/2014 2:29:42 PM Received Date: 7/7/2014 2:29:00 PM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients:
"'lawrence.rudy@duke-energy.com'" <lawrence.rudy@duke-energy.com>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 672 7/7/2014 2:29:00 PM DRAFT Catawba 1-2 RR 14-CN-001 RAI.docx 35125 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DRAFT REQUEST FOR ADDITIONAL INFORMATION REGARDING CATAWBA NUCLEAR STATION, UNITS 1 AND 2 RELIEF REQUEST SERIAL NUMBER 14-CN-001 LIMITED VOLUMETRIC EXAMINATION OF CLASS 1 WELDS DOCKET NOS. 50-413 AND 50-414 By letter dated February 20, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14052A387), Duke Energy Carolinas (Duke) submitted relief request 14-CN-001. Pursuant to 10 CFR 50.55a(g)(5)(iii), the request sought relief from the volumetric examination coverage requirements of the ASME Code,Section XI. In order for the NRC staff to complete its review of the relief request, the following additional information is requested.
RAI 1
The NRC compared the volumetric examination coverage amounts obtained during the third 10-year inservice inspection (ISI) interval for the nine welds identified in Table 1 in Duke Energys Relief Request 14-CN-001, and compared them to the coverage amounts obtained during the second 10-year ISI interval examinations. The NRC noted significant differences in the coverage amounts for the CNS Units 1 and 2 pressurizer surge nozzle to head welds, as summarized in Table 1.
- a. Explain the rationale for using the different scan angles to examine the pressurizer surge nozzle to head welds for both CNS units that led to the significantly different amount of coverage observed for these welds.
- b. Explain the capability of the 35 degree scan angle to adequately detect flaws in the pressurizer surge nozzle to head welds compared to the standard 45 degree and 60 degree scan angles.
- c. The figures in 14-CN-001 associated with this component indicate welds that have been ground flush. Clarify the surface condition of the welds and whether credit was taken for scans performed over the welds.
ENCLOSURE
Table 1. Pressurizer Surge Nozzle to Head Weld Examination Coverage Amounts 2nd ISI Interval 3rd ISI Interval CNS Coverage and Scan Change Weld Coverage and Scan Unit Angles in Coverage Angles (1)
[Date of Exam, Source]
1 1-PZR-W1 81.4 % 77.2 % + 4.2 %
[2005, September 8, 2005 Relief Request (ML052590564)]
Scan angles used: Scan angles used:
35°, 45°, 60° 35°, 45° 2 2-PZR-W1 81.2 % 42.8 % + 38.4 %
[2001, December 20, 2001 Relief Request (ML0203300121)]
Scan angles used: Scan angles used:
35°, 45°, 60° 60°, 70° Note: (1) Source: Relief Request 14-CN-001 (ML14052A387).