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Category:Letter
MONTHYEARML24289A1232024-10-24024 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 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 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) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 05000260/LER-2024-002, High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation2024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision 05000296/LER-2024-002, Breaker Trip Automatically Started an Emergency Diesel Generator2024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-09-03
[Table view] Category:Notice of Violation
MONTHYEARIR 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 05000259/20204032020-03-16016 March 2020 Final Significance Determination of Greater than Green Finding, Notice of Violation, and Assessment Followup Letter 05000259/2020403, 05000260/2020403 and 05000296/2020403 IR 05000259/20160152016-11-28028 November 2016 Browns Ferry Nuclear Plant - Notice Of Violation And Proposed Imposition Of Civil Penalty - $140,000, NRC Inspection Report 05000296/2016015 And Investigation Report No. 2-2015-037 IR 05000296/20160152016-11-28028 November 2016 Notice of Violation and Proposed Imposition of Civil Penalty - $140,000, NRC Inspection Report 05000296/2016015 and Investigation Report No. 2-2015-037 IR 05000260/20160142016-10-28028 October 2016 Inspection Report 05000260/2016014; Investigation Report No. 2-2015-008; and Notice of Violation IR 05000259/20160142016-10-28028 October 2016 Browns Ferry Nuclear Plant - Inspection Report 05000260/2016014; Investigation Report No. 2-2015-008; and Notice of Violation IR 05000296/20160132016-07-27027 July 2016 IR 05000296/2016013, Investigation Report 2-2015-037 Apparent Violations, March 11, 2016 IR 05000259/20160132016-07-27027 July 2016 Browns Ferry, IR 05000296/2016013, Investigation Report 2-2015-037 Apparent Violations, March 11, 2016 IR 05000259/20140022014-04-30030 April 2014 Integrated Inspection Report, Final Significance Determination of White Finding and Notice of Violation 05000259-14-002, 05000260-14-002, and 05000296-14-002 IR 05000259/20130132013-08-23023 August 2013 IR 05000260-13-013, and Notice of Violation, 05/14/2013, Browns Ferry Nuclear Plant, Final Significance Determination of White Finding IR 05000260/20130132013-08-23023 August 2013 IR 05000260-13-013, and Notice of Violation, 05/14/2013, Browns Ferry Nuclear Plant, Final Significance Determination of White Finding IR 05000259/20120132012-08-13013 August 2012 Browns Ferry Final Significance Determination of White Finding and Notice of Violation Follow-Up Assessment Letter ML12226A6472012-08-13013 August 2012 Final Significance Determination of White Finding and Notice of Violation Follow-Up Assessment Letter IR 05000259/20120102012-01-23023 January 2012 IR 05000259-12-010, 05000260-12-010 & 05000296-12-010 and Notice of Violation on 09/23/11, Browns Ferry IR 05000259/20110022011-05-13013 May 2011 IR 05000259-11-002, 05000260-11-002, 05000296-11-002 & 07200052-11-002, on 01/01/2011 - 03/31/2011, Browns Ferry, Units 1, 2 & 3, NRC Integrated Inspection and Notice of Violation ML1112904822011-05-0909 May 2011 EA-11-018, Browns Ferry, Final Signficance Determination of Red Finding, Notice of Violation and Assessment Follow-up Letter 2011008 ML1106106412011-03-0202 March 2011 NRC Report 05000259/2010005, 05000260/2010005, and 05000296/2010005; Preliminary Greater than Green Finding Browns Ferry Nuclear Plant ML1106107392011-02-24024 February 2011 Information Related to the Safety Significance of the Apparent Violation Concerning Failure of Unit 1 Residual Heat Removal System Low Pressure Injection Valve ML1104004312011-02-0909 February 2011 Inspection Report 2010-005 and Notice of Violation IR 05000259/20100042010-10-29029 October 2010 IR 05000259-10-004, 05000260-10-004, 05000296-10-004 & 07200052-10-003, and Notice of Violation, 07/01/10 - 09/30/10, Browns Ferry, Integrated Report 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 ML0710303112007-04-13013 April 2007 Notice of Violation (Office of Investigations Report 02-2005-006) 2023-05-08
[Table view] |
Text
May 8, 2023
SUBJECT:
BROWNS FERRY NUCLEAR PLANT-FINAL SIGNIFICANCE DETERMINATION OF A WHITE FINDING AND NOTICE OF VIOLATION AND ASSESSMENT FOLLOWUP LETTER; NRC INSPECTION REPORT 05000259/2023091
Dear Mr. James Barstow:
This letter provides you the final significance determination of the preliminary White finding discussed in the U.S. Nuclear Regulatory Commission (NRC) inspection report (IR)
05000259/2023090 dated March 2, 2023 (Agencywide Documents Access and Management System (ADAMS), Accession Number ML23048A062). The finding is associated with an NRC-identified apparent violation of Title 10 of the Code of Federal Regulations (10 CFR)
Part 50, Appendix B, Criterion XVI, Corrective Action for the failure to promptly identify and correct a condition adverse to quality associated with the electric governor remote (EG-R) and remote servo subcomponents. This failure resulted in the inoperability of the Browns Ferry Unit 1 high pressure coolant injection (HPCI) system on July 12, 2022.
In a letter dated April 11, 2023, Browns Ferry Nuclear Plant, Units 1 and 2 - Response to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000259/2023090 and 05000260/2023090, EA-22-122 (ADAMS Accession Number ML23101A025), you provided a response to the NRC staffs preliminary determination regarding the finding. You agreed that this condition existed as documented in the inspection report and you neither contested the significance of the finding nor the apparent violation.
Furthermore, your response clarified that the updated condition monitoring standards of 0.05 percent moisture content in governor control oil was not established by the Terry Turbine Users Group (TTUG) in their August 2021 virtual conference as described in NRC IR 05000259/2023090. You do acknowledge that while this topic, the adverse impact on governor control oil with moisture content in excess of 0.05 percent, was discussed at the August 2021 conference attended by your staff, the new monitoring standards were not considered established until the Electric Power Research Institute (EPRI) published The Effects of Moisture in Terry Turbine Lube Oil and Governor Systems on December 3, 2021. The NRC has accepted this clarification regarding the moisture content monitoring standards. Due to the failure mechanism of corrosion, a definitive elapsed time for component inoperability could not be determined. Therefore, the NRC has decided not to issue a Browns Ferry Unit 1 Technical Specification Limiting Condition for Operation (LCO) 3.5.1.C violation for HPCI system inoperability related to the July 12, 2022 event.
You have 30 calendar days from the date of this letter to appeal the staffs determination of the significance of the finding. Such appeal will be considered to have merit only if they meet the criteria given in the Inspection Manual Chapter (IMC) 0609, Attachment 2. An appeal must be sent in writing to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region II; the Director, Office of Enforcement; and the NRC resident inspector at Browns Ferry Nuclear Plant.
The NRC has also determined that this failure to identify and correct a condition adverse to quality which resulted in the inoperability of the Browns Ferry Unit 1 HPCI is a violation of 10 CFR 50, Appendix B, Criterion XVI, as cited in the enclosed Notice of Violation (Notice). The circumstances surrounding the violation were described in detail in NRC IR 05000259/2023090.
In accordance with the NRC Enforcement Policy, the Notice is considered an escalated enforcement action because it is associated with a White finding.
The NRC has concluded that the information regarding the reason for the violation, the corrective actions taken as well as those planned to correct the violation and prevent recurrence, and the date when full compliance will be achieved is already adequately addressed on the docket in a letter dated April 11, 2023, Browns Ferry Nuclear Plant, Units 1 and 2 -
Response to Preliminary White Finding and Apparent Violation in NRC Inspection Report 05000259/2023090 and 05000260/2023090, EA-22-122 (ADAMS Accession Number ML23101A025). Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position.
For administrative purposes, this letter is issued as a separate NRC Inspection Report No. 05000259/2023091. Accordingly, apparent violation (AV)05000259/2023090-01 is updated consistent with the regulatory positions described in this letter, as NOV 05000259/2023090-01 in the Mitigating Systems Cornerstone with a safety significance of White with cross-cutting aspect P.2 - Evaluation.
The NRC has determined that the current plant performance places Browns Ferry Nuclear Plant, Unit 1 in the Regulatory Response Column of the Reactor Oversight Process Action Matrix beginning in the First Quarter of 2023 (January 1, 2023). Therefore, the NRC plans to conduct a supplemental inspection in accordance with Inspection Procedure (IP) 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area. This IP is conducted to provide assurance that the root and contributing causes for the performance issues are understood, and to provide assurance that the corrective actions are sufficient to address the root and contributing causes and prevent recurrence. This inspection will be scheduled after you notify the NRC of your readiness. This letter supplements, but does not supersede, the annual assessment letter issued on March 1, 2023 (ML23058A119).
In accordance with 10 CFR 2.390 of the NRC's Rules of Practice and Procedure, a copy of this letter, its enclosure, and your response, if you choose to provide one, will be made available electronically for public inspection in the NRC Public Document Room or from ADAMS, accessible from the NRC Web site at http://www.nrc.gov/readingrm/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.
Sincerely, Signed by Dudes, Laura on 05/08/23 Laura A. Dudes Regional Administrator Docket No. 05000259 License No. DPR-33 Enclosure:
Notice of Violation cc w/ encl: Distribution via LISTSERV
ML23115A000 X Non-Sensitive X Publicly Available X SUNSI Review Sensitive Non-Publicly Available OFFICE RII:DRP RII:DRP RII:DRP RII:DRP RII:RC NAME J. Steward S. Ninh L. McKown L. Suggs S. Price DATE 4/25/2023 4/25/2023 4/25/2023 4/27/2023 4/28/2023 OFFICE RII:EICS HQ:OE HQ:NRR HQ:DRA RII:ORA NAME M. Kowal G. Gulla R. Felts M. Franovich L. Dudes DATE 4/25/2023 5/1/2023 5/1/2023 5/1/2023 5/8/2023
NOTICE OF VIOLATION Tennessee Valley Authority (TVA) Docket No.: 05000259 Browns Ferry Nuclear Plant, Unit 1 License No.: DPR-33 EA-22-122 During an NRC inspection conducted from January 1, 2023 to February 1, 2023, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
10 CFR 50, Appendix B, Criterion XVI requires, in part, measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
Section 10.2.2, Corrective Action for Adverse Conditions of the Nuclear Quality Assurance Plan (NQAP) (Quality Assurance Program Description), of TVA fleet procedure TVA-NQA-PLN89-A, Rev.0040, states in part, that TVA Nuclear and onsite non-nuclear service organizations performing quality-related activities at nuclear facilities shall promptly identify and resolve adverse conditions.
Section 5 of TVA fleet procedure NPG-SPP-22.300.1, Corrective Action Program (BFN Only), Rev. 0000, defines that condition adverse to quality (CAQ) is a condition associated with a structure, system, component or program that is in-scope of the Nuclear Quality Assurance Plan (NQAP). The high-pressure coolant injection system is a safety-related system and is in the scope of the NQAP.
Browns Ferry site procedure Mechanical Preventive Instruction, MPI 0-073-TRB001, High Pressure Coolant Injection (HPCI) Turbine Preventive Maintenance, Revision 0053, Section 6.2.5, states, in part, that internal corrosion or moisture contamination requires initiation of a condition report.
Contrary to the above, from October 27, 2018, to July 12, 2022, the TVA failed to promptly identify and correct the condition adverse to quality associated with the EG-R and remote servo subcomponents. Specifically, the licensee failed to promptly document and correct adverse conditions during the preventive maintenance internal inspection of the EG-R on October 27, 2018, wherein inspection activities identified rust and moisture, but failed to initiate a required CAQ CR in accordance with MPI-0-073-TRB001 and TVA-NQA-PLN89-A.
This violation is associated with a White Significance Determination Process finding.
The NRC has concluded that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence and the date when full compliance was achieved is already adequately addressed on the docket in your written response of April 11, 2023 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML23101A025). However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201 if the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to respond, clearly mark your response as a Reply to a Notice Enclosure
of Violation, include the EA number, and send it to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001 with a copy to the Regional Administrator, Region 2, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice).
If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.
If you choose to respond, your 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.
Therefore, to the extent possible, the response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days of receipt.
Dated this 8th day of May 2023