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Category:Confirmatory Action Letter (CAL)
MONTHYEARML13232A1052013-08-22022 August 2013 Confirmatory Action Letter - Browns Ferry Nuclear Plant, Units 1, 2, and 3, Commitments Related to the Integrated Improvement Plan 2013-08-22
[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-24-009, 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-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-24-081, 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 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 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter 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 IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations 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 REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257 August 22, 2013 EA 13-185 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 3D-C Chattanooga, TN 37402-2801
SUBJECT:
CONFIRMATORY ACTION LETTER - BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3, COMMITMENTS RELATED TO THE INTEGRATED IMPROVEMENT PLAN
Dear Mr. Shea:
This letter confirms the commitments made by the Tennessee Valley Authority (TVA) to the US Nuclear Regulatory Commission (NRC) in an August 9, 2013, letter, Commitments Related to the Browns Ferry Integrated Improvement Plan (Agencywide Documents Access and Management Systems (ADAMS) Accession No. ML13224A263). These commitments are associated with the issues identified during the NRCs 95003 Inspection, Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs or One Red Input, and implementation of the Browns Ferry Nuclear (BFN)
Integrated Improvement Plan (IIP).
TVA notified the NRC staff of its intent to commit to specific actions at BFN that are necessary for the NRC to be able to assess the issues identified during the 95003 inspection for continued improvement in plant performance, and ensure that revisions to the IIP, including defining the timeline for transition out of the IIP to normal improved business practices, are effectively implemented and appropriate.
The NRC reviewed TVAs commitments, including the schedule for completion of items and planned key activities, and determined that TVAs actions, when implemented and then validated by the NRC, will provide the NRC with the necessary assessment bases to evaluate transition of BFN Unit 1 out of Column 4 of the Agency Action Matrix. Transition out of Column 4 would occur when an assessment follow-up letter is issued subsequent to the Reactor Oversight Process assessment in accordance with Inspection Manual Chapter 0305, Section 10.02.d.5.
It is our understanding that TVA will:
- 1) Implement a specific set of actions that will be completed in the near term, referred to as Tier 1 Commitments. These actions will be completed by the dates specified in the Enclosure to the TVA letter Commitments Related to the Browns Ferry Integrated Improvement Plan. The Tier 1 commitments are designated as items 1 through 10.
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- 2) When the Tier 1 actions, items 1 through 10, are completed by TVA and verified to be adequate by the NRC, they will reasonably serve to inform the NRC's decision making regarding closure of the Red Finding and the transition of BFN Unit 1 out of the Multiple/Degraded Cornerstone Column consistent with the NRC's Reactor Oversight Process.
The NRC will conduct follow-up inspections to verify the status of the Tier 1 Commitment items to assess whether or not the items have been implemented adequately.
Pursuant to Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, you are required to:
- 1) Notify me in writing immediately if your understanding differs from that set forth above;
- 2) Notify me in writing if for any reason you cannot complete the Tier 1 actions within the specified schedule and of your modified schedule in advance of the change;
- 3) Notify me in writing if you intend to change, deviate from, or not complete any of the documented commitments, prior to the change or deviation; and Issuance of this Confirmatory Action Letter does not preclude issuance of an order formalizing the above commitments or requiring other actions on the part of the licensee; nor does it preclude the NRC from taking enforcement action for violations of NRC requirements that may have prompted the issuance of this letter. In addition, failure to meet the commitments in this Confirmatory Action Letter may result in the issuance of an order if your performance, as demonstrated by the failure to meet the Confirmatory Action Letter commitments, does not provide reasonable assurance that TVA can meet the NRCs requirements and protect public health and safety.
This Confirmatory Action Letter will remain in effect until BFN has notified the NRC that the Tier 1 Commitments list of actions are complete and successful NRC follow up inspections have been completed.
Additionally, for the items listed as Tier 2 Commitments in the TVA letter Commitments Related to the Browns Ferry Integrated Improvement Plan, the NRC requests that you provide written correspondence informing the NRC when you have completed each of the actions addressed on the Tier 2 list of commitments, items 11 through 31. The NRC requests that this correspondence include the basis for closing of the commitment item in the context of the internal TVA reviews established in the IIP. NRC acknowledges TVAs commitment to complete the Tier 2 items to ensure sustained excellent performance and the achievement of the long term success criteria established in the IIP. The completion of the Tier 2 Commitment actions will be subject to inspection as part of the routine base line ROP inspection program.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and any response will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your
J. Shea 3
response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.390(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Sincerely,
/RA/
Victor M. McCree Regional Administrator Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68 cc: Distribution via Listserv:
__ ML13232A105 ____________
X SUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RIII:DRS RII:DRP RII:DRP RII:DRP RII:OGC NRR/DIRS NRR/DIRS SIGNATURE
/VIA E-mail/
/RA/
/RA/
/RA/
/RA/
/VIA E-mail/
/VIA E-mail/
NAME RSkokowski EGuthrie WJones RCroteau CEvans R.Franovich CRegan DATE 8/19/2013 8/15/2013 8/15/2013 8/15/2013 5/15/2013 8/19/2013 8/19/2013 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICE NRR RII:ORA RII:RA SIGNATURE
/VIA E-mail/
/RA/
/RA/
NAME ELeeds LWert VMcCree DATE 8/22/2013 8/20/2013 8/22 /2013 E-MAIL COPY?
YES NO YES NO YES NO YES NO YES NO YES NO YES NO
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Letter to Joseph W. Shea from Victor M. McCree dated August 22, 2013
SUBJECT:
CONFIRMATORY ACTION LETTER - BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3, COMMITMENTS REGARDING 95003 INSPECTION RELATED ISSUES AND BROWNS FERRY NUCLEAR PLANT TRANSITION OUT OF THE PERFORMANCE IMPROVEMENT PLAN DISTRIBUTION:
C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource DEDO R. Hannah J. Ledford J. Pelchet