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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
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)
ML24029A1132024-01-16016 January 2024
Notification of Inspection and Request for Information (Email)
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
ML23192A0552023-07-11011 July 2023
Relief Request Later Edition of ASME Code for ISI
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)
ML23087A0282023-03-27027 March 2023
Acceptance of Requested Licensing Action Amendment TSTF-505
ML23087A2492023-03-27027 March 2023
50.69 Acceptance Email
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)
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)
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
ML22291A4602022-10-17017 October 2022
Relief Request Impractical RPV and Rx Coolant Sys. Welds
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)
ML22242A1602022-08-30030 August 2022
Hardship Relief Request Pilot-Operated Relief Valve Acceptance Review Results
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
ML22049B0152022-02-17017 February 2022
NRC RP Inspection Document Request Letter
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
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
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
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)
2024-07-24
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NRR-PMDAPEm Resource From: Miller, Ed Sent: Wednesday, September 24, 2014 11:45 AM To: 'randy.hart@duke-energy.com'; 'lawrence.rudy@duke-energy.com'
Subject:
Draft RAI for DPC-NE-3001-P LAR Attachments: SNPB_RAI 2.docx Randy/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: 1589 Mail Envelope Properties (9C2386A0C0BC584684916F7A0482B6CA01016B2CD7C7)
Subject:
Draft RAI for DPC-NE-3001-P LAR Sent Date: 9/24/2014 11:45:02 AM Received Date: 9/24/2014 11:45:00 AM From: Miller, Ed Created By: Ed.Miller@nrc.gov Recipients:
"'randy.hart@duke-energy.com'" <randy.hart@duke-energy.com>
Tracking Status: None
"'lawrence.rudy@duke-energy.com'" <lawrence.rudy@duke-energy.com>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 673 9/24/2014 11:45:00 AM SNPB_RAI 2.docx 23314 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 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 LICENSE AMENDMENT REQUEST METHODOLOGY REPORT DPC-NE-3001-P, REVISION 1 DOCKET NOS. 50-369, 50-370, 50-413, AND 50-414 By letter dated November 14, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13325B142), Duke Energy Carolinas, LLC (Duke, the licensee),
submitted a license amendment request for Catawba Nuclear Station, Units 1 and 2, and McGuire Nuclear Station, Units 1 and 2. The proposed amendment requested review and approval to the Methodology Report DPC-NE-3001-P, Revision 1, Multidimensional Reactor Transients and Safety Analysis Physics Parameters Methodology. By letter dated June 27, 2014 (ML14183B259), Duke provided a response to NRC staff RAIs on the subject amendment request.
The Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and response and has determined that additional information is needed to complete its review.
SNPB-RAI-1) Please submit the following documents, which were referenced as support for the validation and verification of the models in SIMULATE-3K:
- SSP-98/13, Revision 6, SIMULATE-3K Models & Methodology
- SSP-04/443, Revision 2, SIMULATE-3K Models and Assessment Please also provide the following document, which was referenced in support of the SIMULATE-3 methodology:
- SOA-95/18, SIMULATE-3 Methodology, Advanced Three Dimensional Two-Group Reactor Analysis Code SNPB-RAI-2) The hot full power (HFP) steam line break (SLB) analysis is initiated from nominal conditions, according to Section 5.3.1, because it uses the statistical core design (SCD) methodology described in DPC-NE-2005P-A. This is appropriate for departure from nucleate boiling ratio (DNBR) analysis, because the uncertainties have been statistically convoluted into the DNBR limit.
Duke appears to use the same analysis to check the fuel centerline temperature against the centerline fuel melt (CFM) limit. If this reading of the methodology is
correct, please justify use of the nominal SCD initial conditions to be appropriate.
If this reading is incorrect, please clarify the methodology that will be used to calculate fuel centerline temperature and compare to the limit.
SNPB-RAI-3) In Section B2.2.1, Duke proposed the use of an NRC-approved code to account for thermal conductivity degradation (TCD) impacts. What code has been employed for the purpose described in the section, and how is it used?
