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Category:Letter
MONTHYEARML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues 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 ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 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 ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 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 IR 05000327/20234032023-09-14014 September 2023 Cyber Security Inspection Report 05000327/2023403 and 05000328/2023403 (Cover Letter) ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request ML23254A2192023-09-11011 September 2023 Emergency Plan Implementing Procedure Revisions ML23254A0652023-09-0707 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) 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 05000327/20230052023-08-29029 August 2023 Updated Inspection Plan for Sequoyah Nuclear Plant, Units 1 and 2 - Report 05000327/2023005 and 05000328/2023005 ML23233A0122023-08-17017 August 2023 Unit 1 Cycle 25 Refueling Outage - 90-Day Inservice Inspection Summary Report - Supplement ML23233A0142023-08-15015 August 2023 Discharge Monitoring Report (Dmr), July 2023 ML23215A1212023-08-0303 August 2023 301 Exam Administrative Items (2B) Normal Release ML23215A1572023-08-0303 August 2023 Enforcement Action EA-22-129 Inspection Readiness Notification CNL-23-028, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06)2023-08-0202 August 2023 Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 and WBN-TS-23-06) 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 2024-01-04
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML20274A0122020-09-23023 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 2020-09-23
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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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