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Category:Letter
MONTHYEARCNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020)2024-11-12012 November 2024 Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) ML24312A1552024-11-0606 November 2024 Cycle 27 Core Operating Limits Report, Revision 1 IR 05000327/20240032024-11-0606 November 2024 Integrated Inspection Report 05000327/2024003 and 05000328/2024003 CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22)2024-11-0404 November 2024 License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) ML24304A8492024-10-31031 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-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems 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 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 ML24089A0882024-04-18018 April 2024 – Exemption from Select Requirements of 10 CFR Part 73; Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 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 2024-09-08
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML20274A0122020-09-23023 September 2020 Tennessee Valley Authority Reply to Notice of Violation (EA-20-06 and EA-20-07) ML20274A0142020-09-23023 September 2020 TVA Answer to Answer to Notice of Violation (EA-20-06 and EA-20-07) ML20198M4202020-07-0808 July 2020 William Bill Sprinkle, Response to Apparent Violation, IA-20-018 CNL-17-068, Denial of a Non-Cited Violation Involving the Qualification of Class 1E Electrical Equipment and Backfit Claim Proposing the NRC Action Constitutes a Plant-Specific Backfit2017-12-21021 December 2017 Denial of a Non-Cited Violation Involving the Qualification of Class 1E Electrical Equipment and Backfit Claim Proposing the NRC Action Constitutes a Plant-Specific Backfit ML13192A0352013-07-0303 July 2013 Tennessee Valley Authority - Reply to Notices of Violation; EA-13-023 and EA-13-045 ML13080A0742013-03-15015 March 2013 Reply to a Notice of Violation 05000327, 328/2012005-05, Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers IR 05000391/20106032012-07-17017 July 2012 Units 1 & 2 - Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML12202A0102012-07-17017 July 2012 Units 1 & 2 - Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML12172A4122012-06-18018 June 2012 Tennessee Valley Authority - Reply to Notice of Violation 05000391-10-603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML1109605902011-03-31031 March 2011 Response to Notice of Non-Cited Violations - Failure to Use Worst Case 6900 Vac Bus Voltage in Design Calculations. ML0916203332009-06-0909 June 2009 NRC Office Investigations Report 2-2008-024, Sequoyah Nuclear Plant Inspection Report Nos. 05000327/2009007 and 05000328/2009007 and Notice of Violation (NOV) - Reply to NOV EA-08-348 IR 05000327/20090072009-06-0909 June 2009 NRC Office Investigations Report 2-2008-024, Sequoyah Nuclear Plant Inspection Report Nos. 05000327/2009007 and 05000328/2009007 and Notice of Violation (NOV) - Reply to NOV EA-08-348 ML0715801952007-06-0505 June 2007 Reply to Notices of Violation EA-06-269 and EA-06-273 ML0506705062005-02-25025 February 2005 Final Significance Determination for a White Finding and Notice of Violation - NRC IR 05000327-05-007 - Reply to a Notice of Violation, EA-04-223 ML0506000222005-02-25025 February 2005 Final Significance Determination for a White Finding and Notice of Violation - NRC Inspection Report No. 05000327-05-007, Reply to a Notice Violation, EA-04-223 ML0416002752004-06-0303 June 2004 & Watts Bar Nuclear Plant - Interim Safeguards and Security Compensatory Measures Reports & Notices of Violation - Reply to Notices of Violation ML0205803722002-02-0101 February 2002 Forward NRC Office of Investigations Report Number 2-2000-019A and Inspection Report 2024-05-07
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February 25, 2005 U.S. Nuclear Regulatory Commission 10 CFR 2.201 ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket No. 50-327 Tennessee Valley Authority )
SEQUOYAH NUCLEAR PLANT (SQN) - FINAL SIGNIFICANCE DETERMINATION FOR A WHITE FINDING AND NOTICE OF VIOLATION -
NRC INSPECTION REPORT NO. 05000327/2005007 - REPLY TO A NOTICE OF VIOLATION (NOV); EA-04-223 This letter and its enclosure provide TVAs reply to the subject NOV. The NOV contains a violation for failure to identify and correct conditions adverse to quality to preclude the failure of a breaker to operate. The violation is documented in NRCs letter to Mr. K. W. Singer, dated January 26, 2005.
Please direct questions concerning this issue to me at (423) 843-7170 or J. D. Smith at (423) 843-6672.
Sincerely, Original signed by James D. Smith for P. L. Pace Manager, Site Licensing and Industry Affairs Enclosures cc: See page 2
U.S. Nuclear Regulatory Commission Page 2 February 25, 2005 PLP:JDS:JB:KTS cc (Enclosures):
Mr. Douglas V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission Mail Stop O8G9 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2739 Regional Administrator U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, SW, Suite 23&85 Atlanta, Georgia 30303-3415 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624
ENCLOSURE TENNESSEE VALLEY AUTHORITY (TVA)
SEQUOYAH NUCLEAR PLANT (SQN)
UNIT 1 Inspection Report No. 05000327/2005007 Reply To A Notice Of Violation (NOV)
I. RESTATEMENT OF VIOLATION 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.
II. TVAS REPLY TO THE VIOLATION
- 1. Reason For The Violation The reason for failure to identify and correct the bradding of breaker components that resulted in the failure of the 1A RHR breaker to operate was that TVA E-1
did not validate vendor reports and tests, and therefore failed to adequately examine and act upon earlier failure data associated with the Siemens breakers.
On April 25, 2004, a Siemens breaker failed to close during testing. Following this failure, the vendor determined that the failure mechanism was excessive bradding of the mechanism operated cell (MOC) slide bracket on the breaker. The bradding was found to have increased overall thickness of the MOC slide by approximately 0.022 inches. The MOC switches are located in the switchgear cubicle and operated by the breaker through a system of twelve moving parts on the breaker and in the cubicle. As a result of bradding, the MOC slide became wedged between the breaker side sheet and the washers under the head of the MOC slide mounting bolt.
In May 2004, the vendor provided a draft report that stated minor bradding is normal and does not affect breaker operation, and that breakers should be inspected visually or functionally. Additionally, the report stated that functional testing of the MOC operator over its full range of travel is less subjective and more accurate. TVA performed a functional inspection of twelve breakers, which included the MOC operator. None of the twelve breakers exhibited any performance problems. Three of the twelve breakers were found to have minor bradding on the MOC slide. This inspection appeared to support the vendors statement that minor bradding is expected and not an operational problem. As a result, TVA incorrectly concluded that visual inspection would be an appropriate inspection method for identification of potential performance problems related to bradding.
Subsequent TVA breaker inspections of installed breakers applied the visual inspection method. For the subject breaker, the bradding was not detectable by direct visual inspection. The upset metal was approximately 0.007 inch on each side of the bracket, increasing the overall thickness of MOC slide by approximately 0.013 inch. The clearance between the bolted components was found to be approximately 0.002 inch. As a result of the bradding, the MOC slide became wedged between the breaker side sheet and the washers under the head of the MOC slide mounting bolt.
TVA failed to understand that fabrication clearance at the bolted connection concurrent with minor bradding E-2
could result in breaker performance problems, thereby making visual inspection alone inadequate.
An additional cause was the decision to perform the design change using the documentation only Engineering Design Change (EDC) process. The EDC process was selected based on feedback from another TVA plant in their experience with breaker installation. However, there are several barriers in the Design Change Notice (DCN) process that are not included in the documentation only EDC process. The barriers in the DCN process would have likely prevented the failure to validate the vendor design. The Siemens breakers were expected to have the same form, fit, and function as the breakers they replaced. However, the Siemens design resulted in the breaker operation being approximately twice as fast as the breaker being replaced. The additional breaker operating speed increased the force on the MOC switch by a factor of four. The faster operation of the Siemens breaker was not identified in the EDC process and, therefore, the impact to the switchgear was not addressed.
- 2. Corrective Steps That Have Been Taken And The Results Achieved Following failure of the 1A RHR breaker TVA:
a) Replaced Siemens breakers with ABB breakers in safety-related 6.9-kV breaker cubicles with an automatic or accident close function. This action ensured that Siemens breaker issues would not result in additional performance problems before correction of the hardware condition. The ABB breakers are functioning with acceptable reliability.
b) Revised the appropriate Engineering procedure to ensure that information is adequately verified.
The revision provides guidance to have the engineer verify inputs to the basis for operability by using field measurements, testing, or other available means for development of a functional evaluation. This includes information related to vendor inputs.
c) Revised the appropriate design change process procedure to provide additional control for use of documentation only EDCs when used instead of the standard modification process. This would allow E-3
EDCs to be presented to the design review board to ensure that the EDC is the proper process for the change.
- 3. Corrective Steps That Will Be Taken To Avoid Further Violations No additional steps necessary to prevent recurrence.
- 4. Date When Full Compliance Will Be Achieved TVA is in full compliance.
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