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| | issue date = 06/18/2012 | | | issue date = 06/18/2012 |
| | title = Tennessee Valley Authority - Reply to Notice of Violation 05000391-10-603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response | | | title = Tennessee Valley Authority - Reply to Notice of Violation 05000391-10-603-08 - Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - Revised Response |
| | author name = Shea J W | | | author name = Shea J |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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| | page count = 2 | | | page count = 2 |
| }} | | }} |
| See also: [[followed by::IR 05000391/2010603]]
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| =Text= | | =Text= |
| {{#Wiki_filter:Tennessee | | {{#Wiki_filter: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 |
| Valley Authority, 1101 Market Street, Chattanooga, Tennessee | | |
| 37402 June 18, 2012 10 CFR 2.201 ATTN: Document Control Desk U.S. Nuclear Regulatory | | ==Subject:== |
| Commission | | Reply to Notice of Violation 05000391/2010603 Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers - |
| Washington, D.C. 20555-0001 | | Revised Response |
| 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 | | ==References:== |
| License No. NPF-90 NRC Docket No. 50-390 Watts Bar Nuclear Plant, Unit 2 Construction | | : 1. NRC Letter, "Response to Corrective Actions for Watts Bar Unit 2 Notice of Violation (NOV) 05000391/2010603-08," dated May 18, 2012 (ML12139A052) |
| Permit No. CPPR-92 NRC Docket No. 50-391 Subject: Reply to Notice of Violation | | : 2. TVA Letter, Watts Bar Nuclear Plant (WBN) Unit 2 - Reply to Notice of Violation 05000391/2010603 'Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers," dated June 9, 2011 (ML11164A141) |
| 05000391/2010603-08 | | 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 FederalRegulations (10 CFR), Part 50, Appendix B, Criterion III, "Design Control." The NRC requested that TVA amend their response to Printed on recycled paper |
| -Failure to Adequately
| | |
| Evaluate and Qualify Molded Case Circuit Breakers -Revised Response References: | | 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. |
| 1. NRC Letter, "Response | | 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. |
| to Corrective | | 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. |
| Actions for Watts Bar Unit 2 Notice of Violation (NOV) 05000391/2010603-08," dated May 18, 2012 (ML12139A052) | | 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. |
| 2. TVA Letter, Watts Bar Nuclear Plant (WBN) Unit 2 -Reply to Notice of Violation | | If you have any questions relating to this matter, please contact Gene Cobey at 423-751-3275. |
| 05000391/2010603-08 | | I declare under penalty of perjury that the foregoing is true and correct. Executed on the 18th day of June, 2012. |
| -'Failure to Adequately
| | 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}} |
| 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 | |
| }} | |
|
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Category:Letter
MONTHYEARML24219A0262024-08-12012 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) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter 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 IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 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 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 ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 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 IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information 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 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) 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 IR 05000327/20240012024-04-17017 April 2024 Integrated Inspection Report 05000327/2024001 and 05000328/2024001 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) ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report ML24106A0502024-04-12012 April 2024 Discharge Monitoring Report (Dmr), February 2024 ML24100A0162024-04-11011 April 2024 Request for Regulatory Conference (Tennessee Valley Authority - Sequoyah Nuclear Plant) CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements ML24088A0332024-03-28028 March 2024 Request for Regulatory Conference (Tennessee Valley Authority) CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report 2024-08-07
[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] |
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 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 'Failure to Adequately Evaluate and Qualify Molded Case Circuit Breakers," dated June 9, 2011 (ML11164A141)
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 FederalRegulations (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