|
|---|
Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024
Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve
ML24023A2802024-01-23023 January 2024
Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump
CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions
ML24016A3042024-01-16016 January 2024
Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024
Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47
ML24022A1732024-01-0303 January 2024
Receipt and Availability of the Subsequent License Renewal Application
ML23319A1992024-01-0303 January 2024
Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves
ML23355A2062023-12-21021 December 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23348A3942023-12-14014 December 2023
Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve
IR 05000259/20230102023-12-11011 December 2023
Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010
ML23335A0722023-12-0101 December 2023
Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump
ML23334A2492023-11-30030 November 2023
Site Emergency Plan Implementing Procedure Revision
CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023
Submittal of Fifth 10-Year Interval Inservice Testing Program Plan
ML23331A2532023-11-27027 November 2023
Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions
CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
ML23325A1102023-11-21021 November 2023
Anchor Darling Double Disc Gate Valve Commitment Revision
ML23320A2542023-11-16016 November 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
IR 05000259/20230032023-11-13013 November 2023
Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003
IR 05000259/20230402023-11-0202 November 2023
Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter
ML23292A2532023-10-18018 October 2023
BFN 2024-301, Corporate Notification Letter (210-day Ltr)
ML23282A0022023-10-0606 October 2023
Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump
ML23278A0122023-10-0505 October 2023
Updated Final Safety Analysis Report, Amendment 30
ML23271A1702023-09-28028 September 2023
Site Emergency Plan Implementing Procedure Revision
ML23270A0702023-09-26026 September 2023
SLRA Pre-Application Meeting Summary 09-13-2023
ML23257A1232023-09-22022 September 2023
Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315
CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023
Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision
ML23263B1042023-09-20020 September 2023
Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation
ML23205A2132023-09-0808 September 2023
Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1
CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023
Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64
IR 05000259/20230052023-08-29029 August 2023
Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005
ML23233A0432023-08-18018 August 2023
Enforcement Action EA-22-122 Inspection Readiness Notification
ML23219A1542023-08-17017 August 2023
Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program
ML23228A1642023-08-16016 August 2023
Site Emergency Plan Implementing Procedure Revision
ML23228A0202023-08-15015 August 2023
(BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation
IR 05000259/20230022023-08-10010 August 2023
Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001
ML23192A4472023-07-31031 July 2023
Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information
CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023
Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills
ML23171A8862023-07-24024 July 2023
Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
ML23201A2182023-07-20020 July 2023
Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299)
ML23159A2552023-07-20020 July 2023
Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles
ML23199A3072023-07-18018 July 2023
Site Emergency Plan Implementing Procedure Revision
CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023
Tennessee Valley Authority - Radiological Emergency Plan Revisions
IR 05000259/20233012023-07-18018 July 2023
NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301
2024-02-01
[Table view] |
Text
January 8, 2021
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - MATERIAL CONTROL AND ACCOUNTING PROGRAM INSPECTION REPORT 05000259/2020402, 05000260/2020402 AND 05000296/2020402
Dear Mr. Barstow:
On December 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Browns Ferry Nuclear Plant. On December 15, 2020, the NRC inspectors discussed the results of this inspection with Mr. Christopher D. Dunn and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
The enclosed report contains Security-Related Information, so the enclosed report will not be made publicly available in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390(d)(1). If you choose to provide a response that contains Security-Related Information, please mark your entire response Security-Related Information-Withhold from public disclosure under 10 CFR 2.390 in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). The NRC is waiving the affidavit requirements for your response in accordance with 10 CFR 2.390(b)(1)(ii).
Sincerely,
/RA/
Thomas A. Stephen, Chief Reactor Projects Branch #5 Division of Reactor Projects Docket Nos. 05000259, 05000260 and 05000296 License Nos. DPR-33, DPR-52 and DPR-68 Enclosure:
As stated cc w/o encl: Distribution via LISTSERV ML21011A105____________ (Cover letter)
Cover Letter Only: x Non-Sensitive X Publicly Available x SUNSI Review Sensitive Non-Publicly Available OFFICE RII/DRP/RPB5 RII/DRP/RPB5 RII/DRP/RPB5 NAME S. Ninh M. Kirk T. Stephens DATE 01/07/2021 01/07/2021 01/07/2021
