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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-24-081, Application for Subsequent Renewed Operating Licenses, Third Safety Supplement2024-12-17017 December 2024 Application for Subsequent Renewed Operating Licenses, Third Safety Supplement CNL-24-082, Central Emergency Control Center Emergency Plan Implementing Procedure Revision2024-12-17017 December 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-24-083, 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 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 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 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 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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October 18, 2023 Mr. James Barstow Vice President, Nuclear Regulatory Affairs and Support Services Tennessee Valley Authority 1101 Market Street, LP 4A-C Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT - NOTIFICATION OF LICENSED OPERATOR INITIAL EXAMINATION 05000259/2024301, 05000260/2024301, 05000296/2024301
Dear Mr. Barstow:
In a telephone conversation on 18 October 2023, between Mr. Michael Schulte, Examination Team Supervisor and Mr. Joseph Viera, Senior Operations Engineer, arrangements were made for the administration of operator licensing examinations at Browns Ferry Nuclear Plant. The on-site preparatory week is scheduled for the week of 15 April 2024. The operating test is scheduled to be administered during the week of 20 May 2024, and, if necessary, the week of 27 May 2024. The written examination is scheduled to be administered the week of 27 May 2024.
As agreed during the telephone conversation, your staff will prepare both the operating test and written examination based on the guidelines in Revision 12 of NUREG-1021, "Operator Licensing Examination Standards for Power Reactors." The NRCs regional office will discuss with your staff any changes that might be necessary before the examinations are administered.
To meet the above schedule, it will be necessary for your staff to furnish the operating test outline by 22 December 2023. Mr. Viera provided the written examination outline to your staff in July 2023. The written examinations, operating tests, and supporting reference materials identified in NUREG-1021, Examination Standard (ES)-2.1, Preparing for Operator Licensing Initial Examinations, will be due by 6 March 2024. Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 55.40(b)(3), an authorized representative of the facility licensee shall approve the examinations and tests before they are submitted to the NRC for review and approval. All materials shall be complete and ready-to-use.
We request that any personal, proprietary, sensitive unclassified, or safeguards information in your response be contained in a separate enclosure and appropriately marked. Delays in receiving the required examination and reference materials, or the submittal of inadequate or incomplete materials, may cause the examinations to be cancelled or rescheduled.
To conduct the requested written examinations and operating tests, it will be necessary for your staff to provide adequate space and accommodations in accordance with ES-4.3, Administering Written Examinations, and to make the simulation facility available on the dates noted above. In accordance with ES-3.5, Administering Operating Tests, your staff should retain the original simulator performance data (e.g., system pressures, temperatures, and
J. Barstow 2
levels) generated during the dynamic operating tests until the NRC takes licensing action on all the applications and any adjudicatory actions on any hearing demands are complete.
ES-1.2, Guidelines for Taking NRC Examinations, contains a number of NRC guidelines for the written examinations and operating tests as they are being administered. Your staff has also agreed to make copies of all examination materials that are necessary for administering the examination.
To permit timely NRC review and evaluation, your staff should submit preliminary reactor operator and senior reactor operator waiver and/or excusal requests (if any) (Office of Management and Budget (OMB) control number 3150-0090) at least 60 days before the first examination date (if possible). Contact Mr. Viera to determine the method for submission of the waiver or excusal requests. Preliminary reactor operator and senior reactor operator license applications (OMB control number 3150-0090) and medical certifications (OMB control number 3150-0024) should be submitted at least 30 days before the first examination date. If the NRC does not receive the preliminary applications at least 30 days before the examination date, a postponement may be necessary. Final, signed applications certifying that all training has been completed and requesting any waivers or excusals, as applicable, should be submitted at least 14 days before the first examination date.
Although the guidelines for waiver or excusal requests call for their receipt at least 30 days before the first examination date (preliminary) and 14 days before the first examination date (final), the requests should be submitted as early as possible in the process (see the 60-day guideline above). Resolutions resulting from verbal inquiries by the facility licensee to the NRC are not binding. Submittals addressing waivers or excusals, or both, should be in writing (i.e.,
using NRC Form 398, Personal Qualifications StatementLicensee, or as directed by Mr.
Viera when contacting him to determine the method for submission). The NRC will document its final decision on whether to grant a waiver or excusal on the final (not preliminary) NRC Form 398 submitted for the applicant. The NRC will not provide its decision until the final application is submitted to the agency.
Paperwork Reduction Act Statement This letter contains information collection requirements that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). These information collections were approved by the OMB, approval number 3150-0018.
The burden to the public for these voluntary information collections is estimated to average 2,250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> per examination or response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the information collections. Send comments regarding this information collection to the FOIA, Library, and Information Collections Branch (T6-A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555 0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the OMB reviewer at: OMB Office of Information and Regulatory Affairs (3150-0018), Attn: Desk Officer for the Nuclear Regulatory Commission, 725 17th Street, NW Washington, DC 20503; e-mail: oira_submission@omb.eop.gov.
Public Protection Notification The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information, unless the document requesting or requiring the collection displays a currently valid OMB control number.
J. Barstow 3
In accordance with 10 CFR 2.390, Public inspections, exemptions, requests for withholding, a copy of this letter and its enclosures will be available electronically for public inspection through the NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible on the NRCs Web site at http://www.nrc.gov/reading-rm/adams.html.
Thank you for your cooperation in this matter. Mr. Schulte has been advised of the policies and guidelines referenced in this letter. If you have any questions about the NRC's examination procedures and guidelines, please contact Mr. Viera at (404) 997-4643, (Internet E-mail:
Joseph.Viera@nrc.gov), or me at (404) 997-4703, (Internet E-mail: Thomas.Stephen@nrc.gov).
Sincerely,
/RA/
Thomas A. Stephen, Chief Operations Branch 1 Division of Reactor Safety Docket Nos.: 50-259, 50-260, 50-296 License Nos.: DPR-33, DPR-52, DPR-68
SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII/DRS/OB RII/DRS/OB RII/DRS/OB NAME DEgelstad JViera TStephen DATE 10/18 /2023 10/18 /2023 10/18 /2023