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MONTHYEARCNL-21-053, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535)2021-07-23023 July 2021 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2, in Support of Atrium 11 Fuel Use (TS-535) Project stage: Request ML21252A0102021-08-30030 August 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Acceptance of License Amendment Request to Transition to ATRIUM-11 Fuel Project stage: Acceptance Review PMNS20220206, Meeting with Tennessee Valley Authority Regarding Framatome Advanced Methodologies for the Browns Ferry Atrium 11 Fuel Transition License Amendment Request2022-03-0707 March 2022 Meeting with Tennessee Valley Authority Regarding Framatome Advanced Methodologies for the Browns Ferry Atrium 11 Fuel Transition License Amendment Request Project stage: Meeting ML22083A0762022-03-24024 March 2022 Summary of March 17, 2022, Closed Meeting with Tennessee Valley Authority to Discuss Recently Identified Errors Potentially Affecting the Browns Ferry Atrium 11 License Amendment Request (EPID L-2021-LLA-0132 Project stage: Meeting CNL-22-044, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-04-0808 April 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) Project stage: Request CNL-22-057, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use2022-05-27027 May 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use Project stage: Request ML22154A4042022-06-0303 June 2022 Unit 3 Cycle 20 Mellla+ Eigenvalue Tracking Data Project stage: Request ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel Project stage: RAI ML21347A0192022-06-0606 June 2022 Request for Withholding Information from Public Disclosure Regarding Confirmatory Calculations Project stage: Withholding Request Acceptance ML22157A3272022-06-13013 June 2022 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML22154A1292022-06-13013 June 2022 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information Project stage: Supplement CNL-22-076, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel2022-07-28028 July 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Project stage: Request CNL-22-083, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). Project stage: Request CNL-22-096, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-09-29029 September 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) Project stage: Request ML22276A1002022-10-0404 October 2022 Request for Withholding Information from Public Disclosure for Supplement 3 to Browns Ferry License Amendment Request to Transition to Atrium 11 Fuel Project stage: Withholding Request Acceptance ML22276A1012022-10-25025 October 2022 Request for Withholding Information from Public Disclosure for Supplement 4 to Browns Ferry License Amendment Request to Transition to Atrium 11 Fuel Project stage: Withholding Request Acceptance CNL-22-100, To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 To Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) Project stage: Request ML22297A2352023-01-10010 January 2023 Request for Withholding Information from Public Disclosure Regarding Use of Atrium 11 Fuel Project stage: Withholding Request Acceptance ML22348A0662023-01-13013 January 2023 Issuance of Amendment Nos. 325, 348, & 308 Regarding Application of Advanced Framatome Methodologies, & Adoption of TSTF Traveler TSTF-564-A, Rev. 2, in Support of Atrium 11 Fuel Use (EPID L-2021-LLA-0132) - Nonproprietary Project stage: Approval ML23026A3182023-01-30030 January 2023 Correction of Safety Evaluation for Amendment Nos. 325, 348, and 308, Application of Advanced Framatome Methodologies, and Adoption of TSTF-564-A, Revision 2 (EPID L-2021-LLA-0132) (Letter) Project stage: Approval ML23010A0932023-02-13013 February 2023 Request for Withholding Information from Public Disclosure for Supplement 7 to Browns Ferry License Amendment Request Transition to Atrium 11 Fuel Project stage: Withholding Request Acceptance ML23045A1192023-02-15015 February 2023 Proprietary Determination Letter Enclosure - Browns Ferry Atrium 11 LAR Supp. 6 Project stage: Approval ML23009B7502023-02-15015 February 2023 Request for Withholding Information from Public Disclosure for Supplement 6 to Browns Ferry License Amendment Request to Transition to Atrium 11 Fuel Project stage: Withholding Request Acceptance ML23046A2632023-02-15015 February 2023 Request for Withholding Information from Public Disclosure for Supplement 6 to Browns Ferry LAR to Transition to Atrium 11 Fuel Project stage: Request 2022-06-03
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Category:Letter
MONTHYEARIR 05000259/20240102024-11-12012 November 2024 Design Basis Assurance Inspection Program Inspection Report 05000259/2024010 and 05000260/2024010 and 05000296/2024010 IR 05000259/20240032024-11-0404 November 2024 Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 CNL-24-043, Application for Subsequent Renewed Operating Licenses, Second Safety Supplement2024-11-0101 November 2024 Application for Subsequent Renewed Operating Licenses, Second Safety Supplement ML24305A1692024-10-31031 October 2024 Site Emergency Plan Implementing Procedure Revision 05000259/LER-2024-003, Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators2024-10-29029 October 2024 Valid Specified System Actuation Caused the Automatic Start of Emergency Diesel Generators 05000259/LER-2024-001-02, Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure2024-10-28028 October 2024 Secondary Containment Isolation Valve Inoperable Due to Mechanical Failure ML24299A2632024-10-25025 October 2024 Response to Apparent Violation in NRC Inspection Report 05000260/2024090, EA-24-075 ML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24308A0042024-10-16016 October 2024 Ahc 24-1578 Environmental Review of the Browns Ferry Nuclear Plant, Units 1, 2 and 3 Subsequent License Renewal Application Limestone County CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) 05000296/LER-2024-003, Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints2024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints 05000259/LER-2024-001-01, Inoperability of Unit 3 Diesel Generator Due to Relay Failure2024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure2024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter ML24151A6322024-05-30030 May 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
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Text
OFFICIAL USE ONLY - PROPRIETARY INFORMATION
January 30, 2023
Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 CORRECTION OF SAFETY EVALUATION FOR ISSUANCE OF AMENDMENT NOS. 325, 348, AND 308 REGARDING APPLICATION OF ADVANCED FRAMATOME METHODOLOGIES, AND ADOP TION OF TSTF-564-A, REVISION 2, SAFETY LIMIT MCPR, IN SUPPORT OF ATRIUM 11 FUEL USE (EPID-L-2021-LLA-0132)
Dear Mr. Barstow:
On January 13, 2023, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 325, 348, and 308 to Renewed Facility Operating Licenses Nos. DPR-33, DPR-52, and DPR-68 for the Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3, respectively (Agencywide Documents Access and M anagement System (ADAMS) Accession No. ML22348A068 (not publicly available; proprietary information)).
Among other things, the amendments revised Browns Ferry Technical Specification (TS) 5.6.5.b, Core Operating Limits Repor t, to allow application of Advanced Framatome Methodologies for determining core operating limits in support of loading Framatome fuel type ATRIUM 11' under the currently licensed Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain.
A non-proprietary version of the amendments was not yet released to the public to allow Tennessee Valley Authority (TVA) the opportunity to confirm the proprietary markings in the safety evaluation (SE). On January 19, 2023, TVA staff notified the NRC staff of several places in the SE that should have been marked as proprietary. The identified text on SE pages 19, 43, 44, 45, 46, 47, 60, 73, 74, and 93 has been corrected to properly mark the text as proprietary.
The text will be redacted in the non-proprietary version of Amendment Nos. 325, 348, and 308, which will be released to the public.
The Enclosure to this letter contains proprietary information. When separated from the Enclosure, this document is decontrolled.
OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION
J. Barstow Additionally, during its review, TVA identified errors or missing text on the SE pages as described below:
Page 25: AREVA ATRIUM 11 should read Framatome ATRIUM 11 Page 46 correction to LPCI line break Page 49: ANP-3934, Appendix A should be ANP-3905, Appendix A Page 82: the condition for 50 percent core power, with 113 percent core flow was omitted Page 87: the maximum MCPR was corrected in ANP-3904, Revision 5, dated July 2022 Page 99: the statement For ECPR values less than should be For ECPR values greater than Page 107: the revision number for Reference 27 is missing Page 108: the date for Reference 36 should be August 2005
The NRC concludes that these corrections do no t change the NRC staffs previous conclusions in the SE, nor do they affect the no significant hazards consideration, as published in the Federal Register on March 8, 2022 (87 FR 13014). The enclosure contains corrected pages 19, 25, 43, 44, 45, 46, 47, 49, 60, 73, 74, 82, 87, 93, 99, 107, and 108 for the proprietary SE for Amendment Nos. 325, 348, and 308. The corrections are denoted by a revision bar in the right margin. These corrections will be reflected in the non-proprietary SE for Amendment Nos. 325, 348, and 308.
If you have any questions regarding this matter, please contact me at (301) 415-1627 or by email at Kimberly.Green@nrc.gov.
Sincerely,
/RA/
Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
Corrected Proprietary SE pages 19, 25, 43, 44, 45, 46, 47, 49, 60, 73, 74, 82, 87, 93, 99, 107, and 108
cc: Listserv/without Enclosure
OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION
ENCLOSURE
CORRECTED PAGES 19, 25, 43, 44, 45, 46, 47, 49, 60, 73, 74, 82, 87, 93, 99, 107, AND 108
FOR PROPRIETARY SAFETY EVALUATION
BY THE OFFICE OF NUCLEAR REACTOR REGULATION
RELATED TO LICENSE AMENDMENT NOS. 325, 348, AND 308
TO RENEWED FACILITY OPERATING LICENSES NOS. DPR-33, DPR-52, AND DPR-68
TENNESSEE VALLEY AUTHORITY
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3
DOCKET NOS. 50-259, 50-260, AND 50-296
This document contains proprietary information pursuant to Section 2.390 of Title 10 of the Code of Federal Regulations
Proprietary information is identified by bolded text enclosed within double brackets shown here (( proprietary text )).
OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION
J. Barstow
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 CORRECTION OF SAFETY EVALUATION FOR ISSUANCE OF AMENDMENT NOS. 325, 348, AND 308 REGARDING APPLICATION OF ADVANCED FRAMATOME METHODOLOGIES, AND ADOPTION OF TSTF-564-A, REVISION 2, SAFETY LIMIT MCPR, IN SUPPORT OF ATRIUM 11 FUEL USE (EPID-L-2021-LLA-0132) DATED JANUARY 30, 2023
DISTRIBUTION:
PUBLIC (w/o Enclosure) RidsNrrDssSfnb Resource PM File Copy RidsNrrDssStsb Resource RidsACRS_MailCTR Resource RidsNrrDexEicb Resource RidsNrrDorlLpl2-2 Resource RidsNrrDraArcb Resource RidsNrrPMBrownsFerry Resource DWoodyatt, NRR RidsNrrLARButler Resource ASallman, NRR RidsRgn2MailCenter Resource ARau, NRR RidsNrrDssSnsb Resource
ADAMS Accession Nos.:
Cover Letter, ML23026A318 Proprietary Enclosure, ML23026A324 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DSS/SFNB/BC(A)
NAME KGreen RButler (PBlechman for) DWoodyatt DATE 1/26/23 1/27/23 1/30/23 OFFICE NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME DWrona KGreen DATE 1/30/23 1/30/23
OFFICIAL USE ONLY - PROPRIETARY INFORMATION