|
---|
Category:Inspection Report Correspondence
MONTHYEARML23219A1432023-07-19019 July 2023 2023 BFN - CGD Inspection Information Request IR 05000259/20114032011-09-14014 September 2011 IR 05000259-11-403, 05000260-11-403, 05000296-11-403, on 08/18/2011, Brown Ferry Nuclear Plant, NRC Security Inspection Report ML1109603322011-04-0606 April 2011 NRC Response to TVA Concerning Disputed NOV in NRC Inspection Report 2010005 ML1016900812010-06-17017 June 2010 Reply to Tennessee Valley Authority Letter Dated 05/18/2010, Regarding Inspection Report No. 05000259-10-007, 05000260-10-007 and 05000296-10-007, Browns Ferry Nuclear Plant ML1010905032010-04-19019 April 2010 IR 05000259-10-007, 05000260-10-007 & 05000296-01-007 for Browns Ferry, Final Significance Determination of Yellow & White Findings & Notice of Violation IR 05000259/20084012008-10-16016 October 2008 IR 05000259-08-401, IR 05000260-08-401, and IR 05000296-08-401, on 07/28/2008 Through 07/31/2008, and 10/02/2008, Browns Ferry Nuclear Plant, NRC Inspection IR 05000253/20072012007-11-0606 November 2007 Security Inspection 05000253-07-201, 05000260-07-201 and 05000296-07-201 on 09/27/2007 for Browns Ferry Nuclear Plant IR 05000259/20074022007-04-0505 April 2007 NRC Physical Security Baseline IR 05000259-07-402, 05000260-07-402 and 05000296-07-402 IR 05000259/20060102006-09-29029 September 2006 NRC Security Inspection Report 05000259/2006010, 05000260/2006010 and 05000296/2006010 IR 05000259/20060072006-08-10010 August 2006 IR 05000259-06-007, on 04/16/2006 - 07/15/2006, Browns Ferry, Unit 1; Integrated Inspection Included Aspects of Licensee Engineering and Modification Activities Associated with Unit 1 Recovery Project IR 05000260/20060152006-07-25025 July 2006 Notification of Browns Ferry Nuclear Plant Component Design Bases Inspection - NRC Inspection Report Nos. 05000260/2006015, & 05000296/2006015 IR 05000260/20030122004-01-16016 January 2004 IR 05000260-03-012 & 05000296-03-012 Completed on 09/09/2003 for Browns Ferry, Physical Security Baseline Inspection Report IR 05000260/20030052003-12-19019 December 2003 Input to Browns Ferry Integrated IR 05000260-03-005 ML18283B5211977-09-21021 September 1977 Response to Inspection Conducted on 08/16-19/1977 & Reported in Inspection Report Nos. 05000259/1977015, 05000260/1977015, & 05000296/1977015 ML18283B5231977-08-22022 August 1977 Response to Inspection Conducted on 07/18-19/1977 & Reported in Inspection Report Nos. 05000259/1977012, 05000260/1977012, & 05000296/1977012 2023-07-19
[Table view] 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 ML24018A2102024-01-19019 January 2024 Oregon State University - Change of Facility Backup Project Manager 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 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation 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 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 2024-02-01
[Table view] |
Inspection Report - - 2007201 ( Security) |
---|
|
|
Text
ber 6, 2007
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - SECURITY INSPECTION 05000259/2007201, 05000260/2007201 AND 05000296/2007201
Dear Mr. OGrady:
On September 27, 2007, the U.S. Nuclear Regulatory Commission (NRC) completed a security baseline inspection at the Browns Ferry Nuclear Plant. The inspection covered one or more of the key attributes of the security cornerstone of the NRCs Reactor Oversight Process. The enclosed inspection report documents the inspection results, which were discussed on September 27, 2007, with you and other members of your staff.
The inspection examined activities conducted under your license as they relate to security and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. No findings of significance were identified.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). However, because of the security-related information contained in the enclosure, and in accordance with 10 CFR 2.390, a copy of this letters enclosure will not be available for public inspection.
Enclosure contains Safeguards Information. Upon removal, this letter is decontrolled. Should you have any questions concerning this letter, please contact us. Your cooperation is appreciated.
Sincerely,
/RA/
Ronald J. Albert, Chief Security Performance Evaluation Branch Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68 Enclosure: NRC Inspection Report No. 05000259/2007201, 05000260/2007201 and 05000296/2007201 (SGI)
cc w/encl: Mr. James O. Mitchell, Site Security Manager Browns Ferry Nuclear Plant Tennessee Valley Authority 18833 Shaw Road Athens, AL 35611 cc w/o encl: Mr. Anthony H. Feltman, Emergency Preparedness Manager Browns Ferry Nuclear Plant Tennessee Valley Authority 18833 Shaw Road Athens, AL 35611 Mr. James M. Walker Alabama Director of Homeland Security P.O. Box 3711 Montgomery, AL 36109-0711 Mr. Kirksey E. Whatley, Director Office of Radiation Control Alabama Department of Public Health The RSA Tower Suite 700 P.O. Box 303017-3017 Montgomery, AL 36130-3017