Letter Sequence RAI |
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MONTHYEARML12110A3362012-03-26026 March 2012
NRR E-mail Capture - Request for Additional Information - McGuire Nuclear Station, Catawba Nuclear Station - 10 CFR 50.46, 30-Day Response Regarding Thermal Conductivity Degradation in the Westinghouse Furnished Realistic ECCS Evaluation
Project stage: RAI
ML12104A0322012-04-16016 April 2012
Closeout of Information Request Pursuant to 10 CFR 50.54(f) Related to the Estimated Effect on Peak Cladding Temperature Resulting from Thermal Conductivity Degradation
Project stage: Other
2012-03-26
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Category:E-Mail
MONTHYEARML24029A1132024-01-16016 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)
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
ML21103A0542021-04-13013 April 2021
NRR E-mail Capture - Extension to Request for Additional Information AMS Topical Report AMS-TR-0720R1
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
2024-01-16
[Table view] |
Text
NRR-PMDAPEm Resource From: Thompson, Jon Sent: Monday, March 26, 2012 11:59 AM To: Hart, Randy; Ashe, Ken Cc: Rudy, Lawrence J; Thomas, Jeff
Subject:
Request for Additional Information - McGuire Nuclear Station, Catawba Nuclear Station - 10 CFR 50.46, 30-DAY RESPONSE REGARDING THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE FURNISHED REALISTIC ECCS EVALUATION
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (CATAWBA 1 AND 2), MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (MCGUIRE 1 AND 2), REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING 10 CFR 50.46, 30-DAY RESPONSE TO INFORMATION REQUEST PURSUANT TO 10 CFR 50.54(F) RELATED TO THE ESTIMATED EFFECT ON PEAK CLADDING TEMPERATURE RESULTING FROM THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE FURNISHED REALISTIC EMERGENCY CORE COOLING SYSTEM EVALUATION (TAC NOS. ME8215-8)
By letter dated February 16, 2012, the US Nuclear Regulatory Commission (NRC) staff issued the subject information request to Duke Energy Carolinas, LLC (the licensee) regarding Catawba 1 and 2 and McGuire 1 and 2. The U.S. Nuclear Regulatory Commission staff has reviewed the licensees response and determined that an RAI is needed in order to complete our review. The enclosed document describes this RAI. A prompt response to these RAI questions is requested by the NRC staff.
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. 50-413, 50-414, 50-369, 50-370
Enclosure:
As stated OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION 10 CFR 50.46, 30-DAY RESPONSE TO INFORMATION REQUEST PURSUANT TO 10 CFR 50.54(F) RELATED TO THE ESTIMATED EFFECT ON PEAK CLADDING TEMPERATURE RESULTING FROM THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE FURNISHED REALISTIC EMERGENCY CORE COOLING SYSTEM EVALUATION DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-413 AND 50-414 1
- 1. Please explain how the 10 CFR 50.46(a)(3) error report enclosed in your response to the NRCs Information Request pursuant to 10 CFR 50.54(f) remains adherent to the WCAP-12945-P-A methodology, which includes a supplement describing the method for fulfilling 10 CFR 50.46(a)(3) re-analysis requirements.
- 2. Compare the results of the thermal conductivity degradation (TCD) and offset sensitivity studies to the fuel rod parameter sensitivity studies discussed in the Code Qualification Document. Please explain any significant discrepancies in the results.
- 3. Your submittal referenced a March 7, 2012 letter sent by Westinghouse Electric Company (Westinghouse) to the NRC.
- a. In the final paragraph on page 2 of 9, the document states, Small differences between the void volumes may exist for rods with the same cladding diameter, however, these differences in void volumes have been compared, and the components of the void volume calculations are either conservative or the changes in void volume are negligible after considering other conservatisms. Core operating conditions and powers were also confirmed to either be bounding, the same, or offset by other margins. The representative fuel temperatures and rod internal pressures are either similar or bound those expected for plant specific calculations.
Provide the results of this comparison for Catawba 1 and 2 and McGuire 1 and 2, including the relevant conclusions and the technical basis supporting those conclusions. For any conclusion that differences in void volume are offset by other conservatisms, list those conservatisms and provide a quantitative estimate of each conservatism, as well as a brief description of the rigor associated with that estimate.
- b. Please provide the values for the coefficients A1 and A2 used in the PAD 4.0 + TCD UO2 thermal conductivity equation.
- c. Please explain any error corrections, code improvements, and miscellaneous code cleanup between the WCOBRA/TRAC and HOTSPOT code versions used in the TCD evaluations and those used in the plants analysis of record (AOR).
- d. What is the thermal conductivity model impact of code version changes in HOTSPOT?
- 4. Explain the differences between the TRANSURANUS and PAD computer codes and the impact of those differences. Provide graphs or other quantified descriptions that aid in explanation.
- 5. Please explain how the changed design values will be verified during operation of the plant, i.e. TS limits, Surveillances, etc. Also, explain what compensatory actions will be taken if a value is found to be outside of the limits assumed in the analysis.
2
Hearing Identifier: NRR_PMDA Email Number: 344 Mail Envelope Properties (0A64B42AAA8FD4418CE1EB5240A6FED174DC77F88B)
Subject:
Request for Additional Information - McGuire Nuclear Station, Catawba Nuclear Station - 10 CFR 50.46, 30-DAY RESPONSE REGARDING THERMAL CONDUCTIVITY DEGRADATION IN THE WESTINGHOUSE FURNISHED REALISTIC ECCS EVALUATION Sent Date: 3/26/2012 11:58:31 AM Received Date: 3/26/2012 11:58:32 AM From: Thompson, Jon Created By: Jon.Thompson@nrc.gov Recipients:
"Rudy, Lawrence J" <ljrudy@duke-energy.com>
Tracking Status: None "Thomas, Jeff" <Jeff.Thomas@duke-energy.com>
Tracking Status: None "Hart, Randy" <Randy.Hart@duke-energy.com>
Tracking Status: None "Ashe, Ken" <Ken.Ashe@duke-energy.com>
Tracking Status: None Post Office: HQCLSTR02.nrc.gov Files Size Date & Time MESSAGE 4618 3/26/2012 11:58:32 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
