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Category:Inspection Report
MONTHYEARIR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 IR 05000327/20240902024-03-19019 March 2024 NRC Inspection Report 05000327-2024090 and 05000328-2024090 and Preliminary Greater than Green Finding and Apparent Violation IR 05000327/20244012024-03-12012 March 2024 – Security Baseline Inspection Report 05000327/2024401 and 05000328/2024401 IR 05000259/20230062024-02-28028 February 2024 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1, 2 - Report 05000259/2023006, 05000260/2023006 and 05000296/2023006 IR 05000327/20230042024-02-12012 February 2024 Integrated Inspection Report 05000327/2023004 and 05000328/2023004 and Apparent Violation IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) IR 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 IR 05000327/20230022023-07-31031 July 2023 Integrated Inspection Report 05000327/2023002 and 05000328/2023002 IR 05000327/20230102023-07-20020 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000327/2023010 and 05000328/2023010 ML23163A0392023-06-13013 June 2023 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000327/2023011, 05000328/2023011) and Request for Information (RFI) IR 05000327/20233012023-05-15015 May 2023 NRC Operator License Examination Report 05000327/2023301 and 05000328/2023301 IR 05000327/20230012023-05-0202 May 2023 Integrated Inspection Report 05000327/2023001 and 05000328/2023001 and Exercise of Enforcement Discretion IR 05000327/20234412023-04-20020 April 2023 Final Significance Determination for a Security-Related Greater than Green Finding, Nov & Assessment Followup Letter, 05000327/2023441 & 05000328/2023441 IR 05000327/20234022023-04-13013 April 2023 Security Baseline Inspection Report 05000327/2023402 and 05000328/2023402 IR 05000327/20220062023-03-0101 March 2023 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2022006 and 05000328/2022006 IR 05000327/20234402023-02-13013 February 2023 NRC Inspection Report 05000327/2023440 and 05000328/2023440; Preliminary Greater than Green and Apparent Violation Cover Letter IR 05000327/20220042023-02-10010 February 2023 Integrated Inspection Report 05000327/2022004 and 05000328/2022004 IR 05000327/20234012023-02-0606 February 2023 Security Baseline Inspection Report 05000327/2023401 and 05000328/2023401 IR 05000327/20224402023-01-17017 January 2023 Special Inspection Report 05000327/2022440 and 05000328/2022440 and Apparent Violation - Cover IR 05000327/20220032022-11-0707 November 2022 Integrated Inspection Report 05000327/2022003 and 05000328/2022003 IR 05000327/20224012022-10-18018 October 2022 Material Control and Accounting Program Inspection Report 05000327/2022401 and 05000328/2022401 IR 05000327/20220052022-08-30030 August 2022 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327 2022005 and 05000328 2022005 - Final IR 05000327/20220022022-08-0101 August 2022 Integrated Inspection Report 05000327 2022002 and 05000328 2022002 IR 05000327/20223012022-07-21021 July 2022 Operator License Examination Report 05000327/2022301 and 05000328/2022301 IR 05000327/20220012022-05-11011 May 2022 Integrated Inspection Report 05000327/2022001, 05000328/2022001 and 07200034/2010002 IR 05000327/20220102022-04-25025 April 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000327/2022010 and 05000328/2022010 IR 05000327/20224022022-03-28028 March 2022 Security Baseline Inspection Report 05000327/2022402 and 05000328/2022402 IR 05000327/20210062022-03-0202 March 2022 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - (Report No. 05000327/2021006 and 05000328/2021006) IR 05000327/20210042022-02-0707 February 2022 Integrated Inspection Report 05000327/2021004 and 05000328/2021004 IR 05000327/20210032021-11-10010 November 2021 Integrated Inspection Report 05000327/2021003 and 05000328/2021003 and Apparent Violation and Exercise of Enforcement Discretion IR 05000327/20210052021-08-18018 August 2021 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 Report 05000327/2021005 and 05000328/2021005 IR 05000327/20210022021-07-27027 July 2021 Integrated Inspection Report 05000327/2021002 and 05000328/2021002 IR 05000327/20210112021-07-19019 July 2021 Biennial Problem Identification and Resolution Inspection Report 05000327/2021011 and 05000328/2021011 IR 05000327/20210012021-04-27027 April 2021 Integrated Inspection Report 05000327/2021001 and 05000328/2021001 IR 05000327/20214012021-04-21021 April 2021 NRC Inspection Report 05000327/2021401 and 05000328/2021401 (U) IR 05000327/20210102021-04-21021 April 2021 NRC Inspection Report 05000327/2021010 and 05000328/2021010 IR 05000327/20200062021-03-0303 March 2021 Annual Assessment Letter for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2020006 and 05000328/2020006 IR 05000327/20200042021-01-29029 January 2021 Integrated Inspection Report 05000327/2020004 and 05000328/2020004 IR 05000327/20204202020-11-20020 November 2020 Security Inspection Report 05000327/2020420 and 05000328/2020420 ML20321A2102020-11-20020 November 2020 Security Inspection Report 05000327/2020420 and 05000328/2020420 - Cover Letter IR 05000327/20200032020-11-10010 November 2020 Integrated Inspection Report 05000327/2020003, 05000328/2020003 and 07200034/2020002 IR 05000327/20200122020-10-20020 October 2020 Plants - Triennial Fire Protection Inspection Report 05000327/2020012 and 05000328/2020012 2024-08-26
[Table view] Category:Letter
MONTHYEARML24304A8492024-10-31031 October 2024 December 2024 Requalification Inspection Notification Letter IR 05000327/20250102024-10-29029 October 2024 Notification of Sequoyah, Units 1 and 2 - Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000327/2025010 and 05000328/2025010 ML24298A1172024-10-24024 October 2024 Cycle 26, 180-Day Steam Generator Tube Inspection Report 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 05000327/LER-2024-001, Reactor Trip Due to a Turbine Trip2024-10-17017 October 2024 Reactor Trip Due to a Turbine Trip ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 05000328/LER-2024-001, Reactor Trip Due to an Electrical Trouble Turbine Trip2024-09-25025 September 2024 Reactor Trip Due to an Electrical Trouble Turbine Trip 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 CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 ML24267A0402024-09-19019 September 2024 Cycle 27 Core Operating Limits Report Revision 0 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 ML24185A1742024-09-18018 September 2024 Cover Letter - Issuance of Exemption Related to Non-Destructive Examination Compliance Regarding Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions ML24247A2212024-08-29029 August 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Letter OG-21-160, NEI 03-08 Needed Guidance: PWR Lower Radial Support Clevis Insert X-750 Bolt Inspection Requirements, September 1, 2021 ML24247A1802024-08-28028 August 2024 Application to Revise the Fuel Handling Accident Analysis, to Delete Technical Specification 3.9.4, Containment Penetrations, and to Modify Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation for Sequoyah Nuclea IR 05000327/20240052024-08-26026 August 2024 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2024005 and 05000328/2024005 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), IR 05000327/20240022024-07-31031 July 2024 Integrated Inspection Report 05000327/2024002 and 05000328/2024002 ML24211A0572024-07-29029 July 2024 Submittal of Emergency Plan Implementing Procedure Revision ML24211A0542024-07-29029 July 2024 Operator License Examination Report ML24211A0412024-07-26026 July 2024 Unit 1 Cycle 26 Refueling Outage - 90-Day Inservice Inspection Summary Report 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 ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24177A0282024-06-25025 June 2024 Emergency Plan Implementing Procedure Revisions ML24176A0222024-06-24024 June 2024 Retraction of Interim Report of a Deviation or Failure to Comply – Transducer Model 8005N 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) ML24145A0852024-05-30030 May 2024 1B-B Diesel Generator Failure - Final Significance Determination Letter ML24145A1052024-05-29029 May 2024 301 Exam Approval Letter ML24134A1762024-05-13013 May 2024 Submittal of 2023 Annual Radiological Environmental Operating Report 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 ML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML24120A0582024-04-26026 April 2024 10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant Units 1 and 2 ML24116A2612024-04-25025 April 2024 Interim Report of a Deviation or Failure to Comply - Transducer Model 8005N ML24114A0482024-04-23023 April 2024 Annual Radioactive Effluent Release Report for 2023 Monitoring Period 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 ML24144A2322024-04-20020 April 2024 Tennessee Multi-Sector Permit (Tmsp), 2024 Annual Discharge Monitoring Report for Outfalls SW-3, SW-3, and SW-9 ML24144A2362024-04-20020 April 2024 Discharge Monitoring Report (Dmr), March 2024 ML24102A1212024-04-18018 April 2024 Summary of Conference Call with Tennessee Valley Authority Regarding Sequoyah Nuclear Plant, Unit 1 Spring 2024 Steam Generator Tube Inspections ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update 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 ML24109A0272024-04-16016 April 2024 Cycle 27 Core Operating Limits Report Revision 0 CNL-23-006, Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03)2024-04-15015 April 2024 Application to Modify Technical Specifications 3.8.1, AC Sources – Operating, and 3.8.2, AC Sources – Shutdown, for Sequoyah Nuclear Plant (SQN-TSC-22-03) ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 2024-09-08
[Table view] Category:Notice of Violation
MONTHYEARIR 05000327/20150082015-03-0909 March 2015 Sequoyah Final EA-14-003 ML15068A1322015-03-0909 March 2015 Final EA-14-003 ML13155A5602013-06-0404 June 2013 Final Determination EA-13-023 and 045 IR 05000327/20130112013-06-0404 June 2013 Sequoyah Final Determination EA-13-023 and 045 IR 05000327/20120052013-02-13013 February 2013 IR 05000327-12-005, 05000328-12-005; 10/1-12/31/2012; Sequoyah Nuclear Plant, Units 1 and 2; (I.E. Adverse Weather Protection, Fire Protection, Inservice Inspection Activities, Refueling and Outage Activities, and Problem Identification and ML0913206232009-05-12012 May 2009 IR 05000327-09-007, IR 05000328-09-007, on 12/16/2008, for Sequoyah, Notice of Violation ML0901600052009-01-15015 January 2009 Notice of Violation and Expiration of License ML0900606072009-01-0505 January 2009 IA-08-038, Hickey, Notice of Violation (Nuclear Regulatory Commission Office of Investigation Report No. 2-2007-025, Sequoyah Nuclear Plant) ML0733808782007-06-20020 June 2007 IA-07-033, Notice of Violation IR 05000327/20050072005-01-26026 January 2005 Final Significance Determination for a White Finding and Notice of Violation (NRC IR 05000327-05-007 Sequoyah Nuclear Power Plant) ML0201004782002-01-10010 January 2002 EA-01-316 & EA-01-317, Sequoyah Nuclear Plant, Notice of Violation 2015-03-09
[Table view] |
Text
ary 26, 2005
SUBJECT:
FINAL SIGNIFICANCE DETERMINATION FOR A WHITE FINDING AND NOTICE OF VIOLATION (NRC INSPECTION REPORT NO. 05000327/2005007, SEQUOYAH NUCLEAR POWER PLANT)
Dear Mr. Singer:
The purpose of this letter is to provide you with the Nuclear Regulatory Commissions (NRC) final significance determination for a finding at your Sequoyah Nuclear Power Plant involving the failure to promptly identify and correct binding problems with the Siemens breaker mechanism operated cell (MOC) slide assembly for the 1A Residual Heat Removal (RHR) pump. On July 7, 2004, the 1A RHR pump failed to start during routine surveillance testing due to MOC slide assembly binding. The failed breaker had been installed in the 1A RHR pump cubicle on April 27, 2004, and was last successfully operated on June 23, 2004.
The finding was documented in NRC Inspection Report (IR) 05000327/2004004 and 05000328/2004004, dated October 25, 2004, and was assessed under the Significance Determination Process (SDP) as a preliminary White issue for Unit 1 (i.e., an issue of low to moderate safety significance, which may require additional NRC inspection). NRC Inspection Report 05000327/2004010, dated December 17, 2004, informed TVA of the NRCs preliminary conclusion, provided TVA an opportunity to request a regulatory conference on this matter, and forwarded the details of the NRCs preliminary estimate of the change in core damage frequency (CDF) for this finding.
In a telephone conversation with Mr. S. Cahill of NRC, Region II, on December 29, 2004, Mr. Paul Pace of your staff indicated that TVA did not contest the risk significance of this finding or the characterization of the issue as a violation, and declined the opportunity to discuss this issue in a regulatory conference. You documented these decisions in a letter dated January 18, 2005.
After considering the information developed during the inspection and provided in your January 18 letter, the NRC has concluded that the inspection 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.
TVA 2 You have 10 business days from the date of this letter to appeal the staffs determination of significance for the identified White finding. Such appeals will be considered to have merit only if they meet the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2.
The NRC also determined that a violation occurred involving the requirements of 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, in that TVA failed to promptly correct a condition adverse to quality. Specifically, TVAs actions in response to the previous MOC linkage problems and the vendors discovery of the binding problem in April of 2004 did not constitute adequate corrective action to preclude the failure of the 1A RHR breaker, which resulted in the failure of 1A RHR pump to start during surveillance testing. Accordingly, a Notice of Violation is included as an enclosure to this letter. In accordance with the NRC Enforcement Policy, NUREG-1600, the Notice of Violation is considered escalated enforcement action because it is associated with a White finding.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with regulatory requirements.
Because plant performance for this issue has been determined to be in the regulatory response band, we will use the NRC Action Matrix to determine the most appropriate NRC response for this event. We will notify you, by separate correspondence, of that determination.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and 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. 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. The NRC also includes significant enforcement actions on its Web site at www.nrc.gov; select What We Do, Enforcement, then Significant Enforcement Actions.
For administrative purposes, this letter is issued as a separate NRC Inspection Report, No.
05000327/2005007, and the above violation is identified as VIO 05000327/2005007-01: Failure to Take Adequate Corrective Actions Regarding Binding of the 1A RHR Pump Breaker.
Accordingly, the associated apparent violation, AV 05000327/2004010-01 and unresolved item, URI 05000327/2004004-02, are closed.
TVA 3 Should you have any questions regarding this letter, please contact Stephen Cahill, Chief, Reactor Projects Branch 6, at (404) 562-4520.
Sincerely,
/RA/
William D. Travers Regional Administrator Docket No.: 50-327 License No: DPR-77 Enclosure: Notice of Violation cc w/encl: (See page 4)
TVA 4 cc w/ encl:
Ashok S. Bhatnagar County Mayor Senior Vice President Hamilton County Courthouse Nuclear Operations Chattanooga, TN 37402-2801 Tennessee Valley Authority Electronic Mail Distribution Ann Harris 341 Swing Loop Larry S. Bryant, General Manager Rockwood, TN 37854 Engineering and Technical Services Tennessee Valley Authority James H. Bassham, Director Electronic Mail Distribution Tennessee Emergency Management Agency Randy Douet Electronic Mail Distribution Site Vice President Sequoyah Nuclear Plant Electronic Mail Distribution General Counsel Tennessee Valley Authority Electronic Mail Distribution John C. Fornicola, Manager Nuclear Assurance and Licensing Tennessee Valley Authority Electronic Mail Distribution Fredrick C. Mashburn Sr. Program Manager Nuclear Licensing Tennessee Valley Authority Electronic Mail Distribution Paul L. Pace, Manager Licensing and Industry Affairs ATTN: James D. Smith Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution David A. Kulisek, Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution Lawrence E. Nanney, Director TN Dept. of Environment & Conservation Division of Radiological Health Electronic Mail Distribution
TVA 5 Distribution w/encl:
L. Reyes, EDO W. Borchardt, NRR L. Chandler, OGC D. Dambly, OGC E. Julian, SECY B. Keeling, OCA Enforcement Coordinators D. Holody RI, K. OBrien RIII, G. Sandborn RIV E. Hayden, OPA G. Caputo, OI H. Bell, OIG C. Carpenter, NRR M. Johnson, NRR R. Franovich, NRR F. Congel, OE L. Plisco, RII V. McCree, RII L. Wert, RII C. Casto, RII H. Christensen, RII R. Bernhard, RII S. Cahill, RII S. Sparks, RII S. Freeman, RII C. Evans, RII B. Carrion, RII R. Hannah, RII K. Clark, RII PUBLIC OEMAIL OEWEB OFFICE RII:DRP RII:DRS RII:EICS RII:DRP OE SIGNATURE SJC RHB CFE VMM FC NAME SCahill RBernhard CFEvans VMcCree FCongel DATE 01/19/2005 01/19/2005 01/19/2005 01/19/2005 01/26/2005 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO PUBLIC DOCUMENT YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: E:\Filenet\ML050260382.wpd
NOTICE OF VIOLATION Tennessee Valley Authority Docket No.: 50-327 Sequoyah Nuclear Plant License No.: DPR-77 Unit 1 EA-04-223 During an NRC inspection completed on September 25, 2004, a violation of NRC requirements was identified. In accordance with the General Statement of Policy and Procedure for NRC Enforcement Actions, (Enforcement Policy), the violation is listed below:
10 CFR 50, Appendix B, Criterion XVI, Corrective Actions, requires in part that measures shall be established to assure that conditions adverse to quality, such as failures and malfunctions, are promptly identified and corrected.
Contrary to the above, from April 27, 2004, through July 7, 2004, the licensee failed to correct conditions adverse to quality. Specifically, a breaker linkage binding/bradding problem that led to the failure of the 1A Residual Heat Removal (RHR) pump to start on demand during surveillance testing on July 7, 2004, was not detected during the visual inspection of the 1A RHR breaker on June 9, 2004. The licensees actions in response to the previous linkage problems and the vendors discovery of the binding problem in April of 2004 did not assure that the condition was identified and corrected to preclude the failure of the 1A RHR breaker to operate during testing.
This violation is associated with a White Significance Determination Process finding for Unit 1.
Pursuant to the provisions of 10 CFR 2.201, TVA is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region II, 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). This reply should be clearly marked as a "Reply to a Notice of Violation; EA-04-223" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation or severity level, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previously docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
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),
to the extent possible, it should not include any personal privacy, proprietary, or safeguards Enclosure
Notice of Violation 2 information so that it can be made available to the public without redaction. ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your 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.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days.
Dated this 26th day of January 2005 Enclosure