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Category:Inspection Report
MONTHYEARIR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 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 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 IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 IR 05000259/20234022023-06-12012 June 2023 Material Control and Accounting Program Inspection Report 05000259 2023402, 05000260 2023402 and 05000296 2023402 IR 05000259/20230912023-05-0808 May 2023 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter; NRC Inspection Report 05000259/2023091 IR 05000259/20230012023-05-0303 May 2023 Integrated Inspection Report 05000259/2023001, 05000260/2023001 and 05000296/2023001 IR 05000259/20234402023-03-23023 March 2023 Special Inspection Supplemental Report 05000259 2023440 and 05000260 2023440 and 05000296 2023440 Cover Letter IR 05000259/20234012023-03-0808 March 2023 Security Baseline Inspection Report 05000259 2023401 and 05000260/2023401 and 05000296/2023401 IR 05000259/20230902023-03-0202 March 2023 NRC Inspection Report 05000259/2023090 and 05000260 2023090 and Preliminary White Finding and Apparent Violation IR 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 IR 05000259/20220042023-02-0707 February 2023 Integrated Inspection Report 05000259/2022004, 05000260/2022004 and 05000296/2022004 IR 05000259/20220032022-11-0909 November 2022 Browns Perry Nuclear Plant - Integrated Inspection Report 05000259/2022003, 05000260/2022003 and 05000296/2022003 IR 05000259/20220122022-09-20020 September 2022 Biennial Problem Identification and Resolution Inspection Report 05000259 2022012, 05000260 2022012 and 05000296 2022012 IR 05000259/20220112022-09-16016 September 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000259/2022011 and 05000260/2022011 and 05000296/2022011 IR 05000259/20224022022-09-0606 September 2022 Security Baseline Inspection Report 05000259/2022402 and 05000260/2022402 and 05000296/2022402 Cover Letter IR 05000259/20220052022-08-30030 August 2022 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005 IR 05000259/20220022022-08-0808 August 2022 Integrated Inspection Report 05000259/2022002, 05000260/2022002 and 05000296/2022002 IR 05000259/20224202022-07-19019 July 2022 Security Baseline Inspection Report 05000259/2022420, 05000260/2022420 and 05000296/2022420 ML22181A9562022-06-29029 June 2022 Bf Report 2022-401 Base Public Cover Letter ML22173A1622022-06-21021 June 2022 Replacement Steam Dryer Visual Inspection Results (U3R20) IR 05000259/20220012022-05-12012 May 2022 Integrated Inspection Report 05000259/2022001, 05000260/2022001, 05000296/2022001 and Exercise of Enforcement Discretion IR 05000259/20220102022-03-30030 March 2022 Triennial Fire Protection Inspection Report 05000259/2022010 and 05000260/2022010 and 05000296/2022010 and Apparent Violation IR 05000259/20224012022-03-0808 March 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401 IR 05000259/20210062022-03-0202 March 2022 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006 IR 05000259/20210042022-01-31031 January 2022 Integrated Inspection Report 05000259/2021004, 05000260/2021004 and 05000296/2021004 IR 05000259/20214032022-01-19019 January 2022 NRC Inspection Report 05000259/2021403, 05000260/2021403 and 05000296/2021403 IR 05000259/20214022022-01-18018 January 2022 Brows Ferry Nuclear Plant - Security Baseline Inspection Report 05000259/2021402 and 05000260/2021402 and 05000296/2021402 IR 05000259/20210032021-11-0909 November 2021 Integrated Inspection Report 05000259/2021003, 05000260/2021003, 05000296/2021003 and 07200052/2021001 IR 05000259/20214012021-08-31031 August 2021 Security Baseline Inspection Report 05000259/2021401 and 05000260/2021401 and 05000296/2021401 IR 05000259/20210112021-08-24024 August 2021 Temporary Instruction 2515/TI-193 Inspection Report 05000259/2021011, 05000260/2021011, and 05000296/2021011 IR 05000259/20210052021-08-23023 August 2021 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005 ML21217A2832021-08-0505 August 2021 Resident Integrated Inspection Report 2021-002 IR 05000259/20213012021-07-28028 July 2021 NRC Operator License Examination Report Nos. 05000259/2021301, 05000260/2021301, 05000296/2021301 IR 05000259/20210102021-07-26026 July 2021 Design Basis Assurance Inspection (Teams) Inspection Report 05000259/2021010 and 05000260/2021010 and 05000296/2021010 IR 05000259/20204012021-05-26026 May 2021 Security Baseline Inspection Report 05000259/2020401 and 05000260/2020401 and 05000296/2020401(U) IR 05000259/20210012021-04-28028 April 2021 Integrated Inspection Report 05000259/2021001, 05000260/2021001 and 05000296/2021001 IR 05000259/20200062021-03-0303 March 2021 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020006, 05000260/2020006 and 05000296/2020006 IR 05000259/20200042021-01-28028 January 2021 Integrated Inspection Report 05000259/2020004, 05000260/2020004, 05000296/2020004, 07200052/2020002 and Exercise of Enforcement Discretion IR 05000259/20204022021-01-0808 January 2021 Material Control and Accounting Program Inspection Report 05000259/2020402, 05000260/2020402 and 05000296/2020402 IR 05000259/20200032020-11-10010 November 2020 Integrated Inspection Report 05000259/2020003, 05000260/2020003 and 05000296/2020003 IR 05000254/20200032020-11-0909 November 2020 Integrated Inspection Report 05000254/2020003; 05000265/2020003 and 07200053/2020001 IR 05000259/20200112020-10-26026 October 2020 Biennial Problem Identification and Resolution Inspection Report 05000259/2020011, 05000260/2020011 and 05000296/2020011 IR 05000259/20204042020-09-29029 September 2020 NRC Security Inspection Report 05000259/2020404 and 05000260/2020404 and 05000296/2020404 and Apparent Violation (U) IR 05000259/20200052020-08-18018 August 2020 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020005, 05000260/2020005, and 05000296/2020005 IR 05000259/20200022020-08-0606 August 2020 Brown Ferry Nuclear Plant Integrated Inspection Report 05000259/2020002, 05000260/2020002, 05000296/2020002, and 07200052/2020001 IR 05000259/20200102020-06-19019 June 2020 Triennial Inspection of Evaluation of Changes, Test and Experiments Baseline Inspection Report 0500259/2020010 and 05000260/2020010 and 05000296/2020010 IR 05000259/20200012020-05-0707 May 2020 Integrated Inspection Report 05000259/2020001, 05000260/2020001, and 05000296/2020001 2023-08-29
[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 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
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION ary 12, 2016
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000259/2015004, 05000260/2015004, AND 05000296/2015004; AND APPARENT VIOLATIONS
Dear Mr. Shea:
On December 31, 2015, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Browns Ferry Nuclear Plant, Units 1, 2, and 3. On January 21, 2016, the NRC inspectors discussed the results of this inspection with Mr. L. Hughes and other members of your staff. Inspectors documented the results of this inspection in the enclosed inspection report.
The enclosed inspection report discusses two findings for which the NRC has not yet reached a preliminary significance determination. As described in Section 4OA3.3 of the enclosed report, two findings related to the failure of the Unit 2 High Pressure Coolant Injection (HPCI) turbine steam admission valve 2-FCV-73-16 packing. The first finding was identified for Tennessee Valley Authoritys (TVA) failure to maintain the design of 2-FCV-73-16 packing assembly. The failure to correctly install the packing gland follower and the use of an incorrect packing type resulted in the development of a progressively degrading high pressure steam leak through the packing gland of 2-FCV-73-16. A second finding was identified for TVAs failure to characterize the steam leak in accordance with procedure NPG-SPP-06.8, Leak Reduction Program, which required it to have been characterized as the highest priority, a Category 1, Severity level 5 leak. This classification would have required an expedited repair of the steam leak.
On September 16, 2015, the packing catastrophically failed requiring isolation of the HPCI steam supply and rendering the system inoperable. This condition initially presented an immediate safety concern based on the size and effects of the resulting steam leak. Prompt operator action to isolate the leak resolved the immediate safety concern. The system has been subsequently returned to service and the circumstances that led to the valve packing degradation no longer exist.
The NRC will inform you in a separate correspondence when the preliminary significance has been determined. We intend to complete and issue our final safety significance determination within 90 days from the date of this letter. The NRCs significance determination process (SDP)
is designed to encourage an open dialogue between your staff and the NRC; however, the
J. dialogue should not affect the timeliness of our final determination. Because the NRC has not made a final determination in this matter, no notice of violation is being issued for these inspection findings at this time.
Additionally, two self-revealing findings of very low safety significance (Green) were identified during this inspection. Each of these findings was determined to involve a violation of NRC requirements. The NRC is treating these violations as non-cited violations (NCVs) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest the violation or significance of the NCVs, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement, U.S.
Nuclear Regulatory Commission, Washington, D.C. 20555-0001; and the NRC Resident Inspector at the Browns Ferry Nuclear Plant.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Browns Ferry Nuclear Plant.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS) component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Alan Blamey, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68
Enclosure:
NRC IR 05000259/2015004, 05000260/2015004 and 05000296/2015004
REGION II==
Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68 Report No.: 05000259/2015004, 05000260/2015004, 05000296/2015004 Licensee: Tennessee Valley Authority (TVA)
Facility: Browns Ferry Nuclear Plant, Units 1, 2, and 3 Location: Corner of Shaw and Nuclear Plant Road Athens, AL 35611 Dates: October 1, 2015, through December 31, 2015 Inspectors: D. Dumbacher, Senior Resident Inspector T. Stephen, Resident Inspector A. Ruh, Resident Inspector S. Roberts, Project Engineer R. Baldwin, Senior Operations Engineer Approved by: Alan Blamey, Chief Reactor Projects Branch 6 Division of Reactor Projects Enclosure
Table of Contents
SUMMARY
REPORT DETAILS
REACTOR SAFETY
1R04 Equipment Alignment 6
1R05 Fire Protection 7
1R06 Flood Protection Measures 8
1R11 Licensed Operator Requalification and Performance 8
1R12 Maintenance Effectiveness 10
1R13 Maintenance Risk Assessments and Emergent
Work Control 11
1R15 Operability Evaluations 13
1R19 Post Maintenance Testing 13
1R20 Refueling and Outage Activities 14
1R22 Surveillance Testing 15
4OA1 Performance Indicator (PI) Verification
15
4OA2 Problem Identification and Resolution
16
4OA3 Event Follow-up
19
4OA5 Other Activities
26
4OA6 Meetings, including Exit
SUPPLEMENTARY INFORMATION
KEY POINTS OF CONTACT
Licensee
- S. Bono, Site Vice President
- L. Hughes, General Plant Manager
- P. Summers, Director of Safety and Licensing
- J. Paul, Nuclear Site Licensing Manager
- M. McAndrew, Manager of Operations
- D. Campbell, Superintendent of Operations
- L. Slizewski, Ops Shift Manager
- M. Kirschenheiter, Assistant Director for Site Engineering
- M. Oliver, Licensing Engineer
- E. Bates, Licensing Engineer
- M. Acker, Licensing Engineer
- R. Guthrie, System Engineer
- M. Lawson, Radiation Protection Manager
- J. Smith, System Engineer
- P. Campbell, System Engineer
- J. Kulisek, EP Manager
- K. Skinner, System Engineer
- L. Holland, System Engineer
- Q. Leonard, System Engineering Manager
- D. Rinne, Program Engineer
- D. Drummonds, Program Engineer
LIST OF ITEMS
OPENED, CLOSED AND DISCUSSED
Opened
- 05000259/260/296/2015004-01 URI High Pressure Fire Protection System Piping Failure Following Pump Start (Section 1R04)
- 05000259/260/296/2015004-03 URI Corrective Actions For 2012 Flooding Walkdowns (Section 4OA2)0500260/2015004-05 AV Failure to Properly Install the Unit 2 HPCI Turbine Steam Admission Valve Packing (Section 4OA3.3)
- 05000260/2015004-06 AV Failure to Identify Significant Steam Leak on the Unit 2 HPCI Turbine Steam Admission Valve. (Section 4OA3.3)
Opened and Closed
- 05000259/260/296/2015004-02 NCV Failure to Properly Manage Risk During Planned Maintenance Activities (Section 1R13)
- 05000260/2015004-04 NCV Failure of 2A RHR Pump to Start from the Control Room due to a Loose Fastener (Section 4OA3.2)
Closed
- 05000259/2015-003-00 LER Loss of Cooling to the Unit 1 and Unit 2 Shutdown Board Rooms Due to Fouled Chiller Coils (Section 4OA3.1)
- 05000260/2015-001-00 LER 2A RHR Pump Start Failure (Section 4OA3.2)
- 05000260/2015-002-00 LER HPCI Turbine Steam Supply Valve Packing Failure (Section 4OA3.3)
LIST OF DOCUMENTS REVIEWED