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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) 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 IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 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 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 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 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 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 ML24253A0152024-09-0808 September 2024 Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation 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 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate 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 IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public 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), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev 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 ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24191A4652024-07-0909 July 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS 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 ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc 2024-09-08
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARML24128A0352024-05-0707 May 2024 Providing Supplemental Information to Apparent Violation ML21027A3942020-12-0707 December 2020 TVA Response to Notice of Violations (EA-19-092) ML20274A0142020-09-23023 September 2020 TVA Answer to Answer to Notice of Violation (EA-20-06 and EA-20-07) ML20274A0122020-09-23023 September 2020 Tennessee Valley Authority Reply 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 L-19-048, Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-0422019-09-12012 September 2019 Response to Apparent Violation in NRC Inspection Report 05000390/2019013 and 05000391/2019013, EA-19-042 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 ML16344A0482016-12-0909 December 2016 Reply to Notice of Violation (EA-16-117) CNL-15-217, Reply to Notice of Violation (EA-15-112)2015-10-16016 October 2015 Reply to Notice of Violation (EA-15-112) CNL-15-152, Reply to Notice of Violation (EA-15-075)2015-07-24024 July 2015 Reply to Notice of Violation (EA-15-075) CNL-15-079, Reply to Notice of Violation (EA-14-179)2015-05-0101 May 2015 Reply to Notice of Violation (EA-14-179) ML13204A3832013-07-18018 July 2013 Reply to Notice of Violation (EA-13-019) 391/2013611-01, -02, and -03 Related to Tva'S Commercial Grade Dedication Program ML13192A0352013-07-0303 July 2013 Tennessee Valley Authority - Reply to Notices of Violation; EA-13-023 and EA-13-045 ML13192A0332013-07-0303 July 2013 Reply to a Notice of Violation; EA-13-018 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 ML12160A3522012-06-0707 June 2012 Reply to Notice of Violation 391/2012612-01 - Failure to Correct a Condition Adverse to Quality Associated with Containment Spray Pump Layup and Preventive Maintenance ML11164A1412011-06-0909 June 2011 Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response ML11105A1502011-04-11011 April 2011 Request for Extension for Time to Respond to Severity Level IV, Non-Cited Violation 05000390-11-008-01 ML1109605912011-03-31031 March 2011 Response to Non-Cited Violations 05000390-10-005-03, Failure to Use Worst Case 6900 Vac Bus Voltage in Design Calculations ML1109605902011-03-31031 March 2011 Response to Notice of Non-Cited Violations - Failure to Use Worst Case 6900 Vac Bus Voltage in Design Calculations. ML1033002172010-11-24024 November 2010 Reply to Notice of Violation 05000391/2010603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers ML1028804932010-10-15015 October 2010 Denial of Notice of Violation (NOV) 05000391-2010603-08, Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Additional Information ML1025204352010-09-0707 September 2010 Denial of Notice of Violation, 05000391/2010603-08, Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers 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 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 ML0908306622009-03-23023 March 2009 Denial of Non-Cited Violation 05000390-08-05-04, Carbon Dioxide System in Fire Area 48 Failed to Meet Design Criterion 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 ML0322000402003-07-25025 July 2003 National Pollutant Discharge Elimination System Permit No.TN0020158 - Response to Notice of Violation ML0316701792003-06-0404 June 2003 National Pollutant Discharge Elimination System (NPDES) Permit No. TN0020168 - Response to Notice of Violation ML0205803722002-02-0101 February 2002 Forward NRC Office of Investigations Report Number 2-2000-019A and Inspection Report 2024-05-07
[Table view] |
See also: IR 05000391/2010603
Text
Tennessee
Valley Authority, 1101 Market Street, Chattanooga, Tennessee
37402 June 18, 2012 10 CFR 2.201 ATTN: Document Control Desk U.S. Nuclear Regulatory
Commission
Washington, D.C. 20555-0001
Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating
License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating
License No. NPF-90 NRC Docket No. 50-390 Watts Bar Nuclear Plant, Unit 2 Construction
Permit No. CPPR-92 NRC Docket No. 50-391 Subject: Reply to Notice of Violation 05000391/2010603-08
-Failure to Adequately
Evaluate and Qualify Molded Case Circuit Breakers -Revised Response References:
1. NRC Letter, "Response
to Corrective
Actions for Watts Bar Unit 2 Notice of Violation (NOV)05000391/2010603-08," dated May 18, 2012 (ML12139A052)
2. TVA Letter, Watts Bar Nuclear Plant (WBN) Unit 2 -Reply to Notice of Violation 05000391/2010603-08
-'Failure to Adequately
Evaluate and Qualify Molded Case Circuit Breakers," dated June 9, 2011 (ML1 1164A141)By letter dated May 18, 2012 (Reference
1), the NRC informed the Tennessee
Valley Authority (TVA) that corrective
actions for Notice of Violation 05000391/2010603-08,"Failure to Adequately
Evaluate and Qualify Molded Case Circuit Breakers," described
in Reference
2, were inadequate
to achieve full compliance
with design control requirements
of Title 10 of the Code of Federal Regulations
(10 CFR), Part 50, Appendix B, Criterion
III, "Design Control." The NRC requested
that TVA amend their response to Printed on recycled paper
U.S. Nuclear Regulatory
Commission
Page 2 June 18, 2012 the NOV (which was issued for Watts Bar Nuclear Plant, Unit 2) with corrective
actions that are sufficient
to achieve full compliance
with NRC regulations.
The NRC further requested
that TVA include in the response, any short-term
operability
and long-term corrective
actions necessary
pursuant to this issue at WBN, Unit 1 and Sequoyah Nuclear Plant (SQN) Units 1 and 2. The NRC stated that the response should specifically
address how configuration
control has been verified for these components
and how applicable
Institute
of Electrical
and Electronic
Engineers (IEEE) standards
are being met for all known Heinemann
molded case circuit breaker configurations
in safety-related applications.
In Reference
1, the NRC stated that TVA is required to submit a supplemental
response to this NOV within 30 days. The NRC further stated that where good cause is shown, consideration
will be given to extending
the response time. TVA is requesting
an extension
for the required submittal
of the supplemental
response to the NOV until July 20, 2012.TVA requests additional
time to prepare a comprehensive
response that fully addresses how configuration
control is verified and conformance
with applicable
IEEE standards are met at each of the four affected units (WBN 1 and 2 and SQN 1 and 2). The additional
time will be used to ensure full coordination
of the response between the construction
and operating
units within TVA.TVA has determined
that the non-conforming
condition
will not prevent the circuit breakers from performing
their WBN Unit 1 and SQN Units 1 and 2 intended safety function.
Documentation
that supports TVA's determination
of operability
is available for inspection
and will be included, as required, in TVA's response to Reference
1.If you have any questions
relating to this matter, please contact Gene Cobey at 423-751-3275.I declare under penalty of perjury that the foregoing
is true and correct. Executed on the 18th day of June, 2012.Respec I J. .hra a ager, Corporate
Nuclear Licensing cc: NRC Regional Administrator
-Region II NRC Senior Resident Inspector
-Sequoyah Nuclear Plant NRC Senior Resident Inspector
-Watts Bar Nuclear Plant, Unit I NRC Senior Resident Inspector
-Watts Bar Nuclear Plant, Unit 2