Letter Sequence Acceptance Review |
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EPID:L-2018-LLA-0048, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information (Open) |
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting
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MONTHYEARCNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 Project stage: Supplement ML18059A1072018-03-16016 March 2018 Maximum Extended Load Line Limit Analysis Plus License Amendment Request Project stage: Request ML18088A0252018-04-0606 April 2018 Acceptance Review Regarding Proposed Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) Project stage: Acceptance Review ML18101A1012018-04-13013 April 2018 Summary of March 16, 2018, Meeting with Tennessee Valley Authority Regarding a License Amendment Request to Implement Maximum Extended Load Line Limit Analysis Plus for Browns Ferry Nuclear Plant Project stage: Meeting CNL-18-099, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results2018-07-23023 July 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 2, Operator Training Results Project stage: Supplement ML18268A0212018-09-27027 September 2018 Regulatory Audit Plan in Support of Maximum Extended Load Line Limit Analysis Plus License Amendment Request Project stage: Other ML18317A1642018-11-20020 November 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - Non-Proprietary Project stage: RAI ML18331A5442018-12-0606 December 2018 Request for Additional Information Regarding Maximum Extended Load Line Limit Plus License Amendment Request (EPID L-2018-LLA-0048) - (Non-Proprietary) Project stage: RAI CNL-18-140, Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 42018-12-13013 December 2018 Response to Request for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 4 Project stage: Supplement CNL-18-139, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information2018-12-14014 December 2018 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Information Project stage: Request CNL-19-011, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results2019-01-16016 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 6, Additional Operator Training Results Project stage: Supplement CNL-19-007, Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus2019-01-16016 January 2019 Response to Requests for Additional Information Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus Project stage: Response to RAI CNL-19-017, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information2019-01-25025 January 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 7, Response to Requests for Additional Information Project stage: Supplement ML19067A0262019-03-0707 March 2019 Notice of Forthcoming Closed Meeting with Tennessee Valley Authority (TVA) and General Electric-Hitachi (Geh), Regarding Maximum Extended Load Line Limit Analysis Plus (Mella+) License Amendment Request (LAR) for Browns Ferry Nuclear Plant, Project stage: Meeting CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information2019-03-13013 March 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information Project stage: Supplement CNL-19-045, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 9, Additional Information Regarding Anticipate Transient Without Scram with .2019-04-24024 April 2019 Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 9, Additional Information Regarding Anticipate Transient Without Scram with . Project stage: Supplement ML19121A2242019-06-0606 June 2019 Non-Proprietary - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Summary Report for the Audits in Support of License Amendment Request for Operation in the Expand Maximum Extended Load Line Limit Analysis Plus Operating Domain Project stage: Other ML19120A2882019-06-0606 June 2019 Summary of March 19, 2019, Closed Meeting with Tennessee Valley Authority a License Amendment Request to Implement Maximum Extended Line Limit Analysis Plus Project stage: Meeting ML19163A0802019-07-22022 July 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML19136A1342019-07-22022 July 2019 Request for Additional Information from Public Disclosure Project stage: RAI ML19136A3282019-07-22022 July 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML19163A1652019-08-0505 August 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML19136A2782019-08-26026 August 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML19136A2542019-08-26026 August 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML19135A5572019-08-26026 August 2019 Request for Withholding Information from Public Disclosure (EPID L-2018-LLA-00488) Project stage: Withholding Request Acceptance ML19133A1192019-08-26026 August 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML19136A0582019-08-26026 August 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance CNL-19-125, Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition2019-12-19019 December 2019 Proposed Technical Specifications (TS) Change 510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 12, Additional License Condition Project stage: Supplement ML19210C3082019-12-26026 December 2019 Redacted - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendment Nos. 310, 333, and 293 Regarding Maximum Extended Load Line Limit Analysis Plus Project stage: Approval ML19360A0442019-12-30030 December 2019 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 2019-01-16
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Category:Acceptance Review Letter
MONTHYEARML20248H5072020-09-0404 September 2020 Acceptance of License Amendment Request to Technical Specification 3.8.6, Battery Cell Parameters ML18088A0252018-04-0606 April 2018 Acceptance Review Regarding Proposed Expanded Maximum Extended Load Line Limit Analysis Plus (Mellla+) ML16007A1632016-01-11011 January 2016 Acceptance Review Regarding Proposed Extended Power Uprate ML13094A3862013-04-0808 April 2013 Acceptance Review Licensing Amendment Request Regarding Additional of Analysis Methodologies to TS 5.6.5 and a Change to Safety Limits Critical Power Ratio for Unit 2 (TAC Nos, MF0877, MF0878 and MF0879) ML12306A4982012-11-0202 November 2012 Acceptance Review of Requested Licensing Action Concerning 25 Percent Surveillance Extension (TAC Nos. ME9485, ME9486, ME9489)(TS-475) ML12275A4922012-10-16016 October 2012 Acceptance Review of Requested Licensing Action Concerning of Low Pressure Coolant Injection Motor-Generator Sets (TAC Nos. ME9176 and ME9177) (TS-429) ML12194A6002012-07-18018 July 2012 Acceptance of Request Licensing Action Concerning Relief Request 2-ISI-29 ML12194A5682012-07-18018 July 2012 Acceptance of Requested Licensing Action Concerning Relief Request 2-ISI-28 ML1101100102010-12-17017 December 2010 Email - Acceptance of Requested Licensing Action Request to Extend Completion Time for TS 3.8.1 Required Action B.4.(TAC No(S). ME5036-8) ML1030801012010-11-0404 November 2010 E-mail Browns Ferry Nuclear Plant Units 1, 2, and 3-Acceptance of Requested Licensing Action-Modification of TS 3.7.3., Control Room Emergency Ventilation System ML0436405562005-01-10010 January 2005 Ltr, Acceptance Review to Extend Technical Specification (TAC No. MC4070, MC4071, MC4072) (TS-447) 2020-09-04
[Table view] Category:Letter
MONTHYEARIR 05000259/20240112024-12-26026 December 2024 Biennial Problem Identification and Resolution Inspection Report 05000259/2024011, 05000260/2024011, and 05000296/2024011 ML24354A2092024-12-19019 December 2024 American Society of Mechanical Engineers, Section XI, Third 10 Year Inspection Interval, Inspection Service, System Procedure Test, Containment Inspection, and Repair and Replacement Programs, Owners Activity Report for Browns Ferry Nuclear CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-24-009, Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations2024-12-17017 December 2024 Brown Ferry Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Plant, Units 1 & 2 - Triennial Decommission Funding Plans for Independent Spent Fuel Storage Installations CNL-24-081, Application for Subsequent Renewed Operating Licenses, Third Safety Supplement2024-12-17017 December 2024 Application for Subsequent Renewed Operating Licenses, Third Safety Supplement CNL-24-083, Alabama Department of Environmental Management Letter2024-12-10010 December 2024 Alabama Department of Environmental Management Letter CNL-24-049, Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements2024-12-0909 December 2024 Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements 05000296/LER-2024-004, Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping2024-12-0404 December 2024 Reactor Coolant System Pressure Boundary Leakage Identified from Recirculation System Small Bore Piping 05000260/LER-2024-002-01, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-11-25025 November 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation IR 05000260/20240912024-11-21021 November 2024 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000260/2024091 ML24324A3332024-11-20020 November 2024 Notification of Licensed Operator Initial Examination 05000259/2025301, 05000260/2025301, 05000296/2025301 IR 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 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 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant 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) 2024-09-03
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 4A Chattanooga, TN 37402-2801 April 3, 2018
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3-ACCEPTANCE REVIEW REGARDING PROPOSED EXPANDED MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS (EPID L-2018-LLA-0048)
Dear Mr. Shea:
By letter dated February 23, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18079B140), as supplemented by letter dated March 7, 2018 (ADAMS Accession No. ML18067A495), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendment would allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus operating domain.
The purpose of this letter is to provide the results of the Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. The acceptance review was performed to determine if there is sufficient technical information, in scope and depth, to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 1 O CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed TVA's submitted information and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite
completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 2500 hours0.0289 days <br />0.694 hours <br />0.00413 weeks <br />9.5125e-4 months <br /> to review the LAR. The NRC staff expects to complete its reviews within 26 months of the date of its submittal, which is April 2020, and that is aligned with the licensee's request for approval of the LAR.
If you have any questions, please contact me at (301) 415-1447 or Farideh.Saba@nrc.gov.
Docket Nos. 50-259, 50-260, and 50-296 cc: Listserv Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML18088A025 OFFICE DORL/LPL! 1-2/
DORL/LPLll-2/LA DSS/SRXB/BC(A)
PM NAME FSaba BClayton JWhitman*
DATE 03/29/18 03/29/18 03/20/18 (Reactor Analyses)
OFFICE DSS/SRXB/
DRA/APHB/
DSS/SCPB/BC BC(A)
BC(A)
NAME JWhitman*
CFong*
RDennig*
DATE 03/23/18 03/15/18 04/03/18 (containment analyses)
OFFICE DSS/STSB/BC DE/EMIB/BC DMLR/MENB/BC NAME VCusmano*
SBailey*
BBeasley*
DATE 03/26/2018 03/23/18 03/30/18