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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
[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
August 13, 2012
EA-12-133 Mr. Joseph Manager, Corporate Nuclear Licensing Tennessee Valley Authority 1101 Market Street, LP 4B-C Chattanooga, TN 37402-2801
SUBJECT: FINAL SIGNIFICANCE DETERMINATION OF WHITE FINDING AND NOTICE OF VIOLATION (NRC INSPECTION REPORT NO. 05000259/2012013, 05000260/2012013, AND 05000296/2012013, BROWNS FERRY NUCLEAR PLANT); FOLLOW-UP ASSESSMENT LETTER
Dear Mr. Shea:
This letter provides you the final significance determination of one preliminary White finding discussed in Nuclear Regulatory Commission (NRC) Inspection Report 05000259/2012007, 05000260/2012007 and 05000296/2012007, dated May 28, 2012, (ML12150A219). The inspection finding was assessed using the NRC's Significance Determination Process and was preliminarily characterized as White, which represents a finding of low to moderate safety significance. The finding involved the failure to adequately accomplish the requirements contained in procedure NPG-SPP-09.3 "Plant Modifications and Engineering Change Control," which required that an evaluation of training needs be completed to support implementation of Design Change Notice (DCN) 69957. Specifically, on September 13, 2011, Procedures 0-SSI-25-1,-2,-3, and -26, "Safe Shutdown Instructions," were issued in support of DCN 69957 without adequately performing an evaluation of training needs. As a result, the systems approach to training was not properly implemented and the procedures could not be satisfactorily performed by plant operators and staff. The NRC's Inspection Report also identified one apparent violation corresponding to this finding.
At your request, a Regulatory Conference was held on July 25, 2012, to discuss your views on this issue. During the meeting, your staff described Tennessee Valley Authority's (TVA) causal analysis and detailed corrective actions both taken and planned. TVA did not contest the NRC's determination of the risk associated with the finding or the characterization as a violation of 10 CFR 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings". A summary of the Regulatory Conference (Accession no. ML12209A391) is available electronically for public inspection from the NRC=s document system (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. After considering the information developed during the inspection, the NRC has concluded that the finding is appropriately characterized as White (i.e. an issue with low to moderate increased importance to safety, which may require additional NRC inspections), in the mitigating systems cornerstone. Details of the NRC's basis for the significance determination are described in NRC Inspection Report 05000259/2012012, 05000260/2012012, and 05000296/2012012; Preliminary White Finding At Browns Ferry Nuclear Plant (ML12174A286). You have 30 calendar days from the date of this letter to appeal the staff's determination of significance for the identified White finding. Such appeals will be considered to have merit only if they meet the criteria given in Inspection Manual Chapter 0609, Attachment 2, Process for Appealing NRC Characterization of Inspection Findings. An appeal must be sent in writing to the Regional Administrator, Region II, 245 Peachtree Center Avenue, NE, Suite 1200, Atlanta, GA 30303-1257. The NRC determined that a violation of 10 CFR 50, Appendix B, Criterion V, "Instructions, Procedures, and Drawings," occurred, as cited in the enclosed Notice of Violation (Notice). In accordance with the NRC's Enforcement Policy, the Notice is considered an escalated enforcement action, because it is associated with a white finding. The circumstances surrounding the violation were described in detail in the subject inspection report. The NRC has concluded that information regarding the reason for the violation, the corrective actions that have already been taken and those actions planned to correct and prevent recurrence, and the date when full compliance was achieved, has been adequately addressed in the information presented by TVA at the Regulatory Conference. Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position.
The NRC assessed the performance at Browns Ferry Nuclear Plant Units 2 and 3 to be in the Regulatory Response Column of the Reactor Oversight Process Action Matrix beginning in the second quarter 2012 based on the White finding discussed in this letter. We will conduct a supplemental inspection (Inspection Procedure 95001, Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area) when you notify us of your readiness for the NRC to review the actions taken to address the White Inspection finding. The assessment of performance does not change for Unit 1 based on the safety significance of this finding, since Unit 1 has been in the Multiple Repetitive Degraded Cornerstone Column of the Reactor Oversight Process Action Matrix since the fourth quarter of 2010.
For administrative purposes, this letter is issued as NRC Inspection Report 05000259/2012013, 05000260/2012013, and 05000296/2012013. AV 05000259/2012007, 05000260/2012007 and 05000296/2012007-05, Failure to Properly Implement the Requirements of the Plant Modifications and Engineering Change Control Procedure, is updated consistent with the regulatory positions described in this letter as VIO 05000259/2012007, 05000260/2012007 and 05000296/2012007-05 with a safety significance of White and a cross-cutting aspect of Work Coordination in the Work Control component of the Human Performance area [H.3.(b)]. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, Enclosure 1, 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/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.
Sincerely,/RA/ Victor M. McCree Regional Administrator Docket Nos.: 50-259, 50-260 and 50-296 License Nos.: DPR-33, DPR-52, DPR-68
Enclosure:
Notice of Violation cc w/encl: (See page 4)