|
|---|
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
[Table view] |
Text
NRR-PMDAPEm Resource From: Miller, Ed Sent: Tuesday, May 20, 2014 7:38 AM To: 'lawrence.rudy@duke-energy.com'
Subject:
Draft RAI for NTTF 2.1 Flooding Hazard Reevaluation Report Attachments: Draft RHMB RAI_Catawba.docx
- Larry, The NRC staffs draft RAI for the subject activity 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; and 3) Whether the information is already available in existing, docketed, correspondence. After youve had a chance to review the draft information request, please contact me to schedule the conference call. Thanks.
Ed Miller (301) 415-2481 1
Hearing Identifier: NRR_PMDA Email Number: 1299 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CAFCB2BB35FF)
Subject:
Draft RAI for NTTF 2.1 Flooding Hazard Reevaluation Report Sent Date: 5/20/2014 7:37:41 AM Received Date: 5/20/2014 7:37:00 AM 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 623 5/20/2014 7:37:00 AM Draft RHMB RAI_Catawba.docx 27432 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DRAFT REQUEST FOR ADDITIONAL INFORMATION CATAWBA NUCLEAR STATION, UNITS 1 AND 2 FLOODING HAZARD REEVALUATION REPORT DOCKET NOS. 50-413 AND 50-414 By letter dated March 12, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14077A054), Duke Energy Carolinas (Duke) submitted a Flooding Hazard Reevaluation Report (FHRR) in response to Enclosure 2 of the March 12, 2012, Fukushima Lessons Learned 50.54(f) letter. In order for the NRC staff to complete its review of the LAR, the following additional information is requested.
- 1. Please submit provide electronic versions of input and output files for the following activities:
- a. Calculations of Locally Intense Precipitation (LIP), Probable Maximum Precipitation, Probable Maximum Flood, dam breach, storm surge, and combined effects flooding.
- b. The Info Works CS (IWCS) model used for LIP site surface depth analysis.
- c. The HEC-RAS model used for reservoir PMF routing and dam break analysis.
- d. The Coastal Engineering Design and Analysis (CEDAS) for wind-driven wave heights.
- e. The COULWAVE model for evaluating overtopping.
