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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML22098A1172022-03-29029 March 2022 Engine Systems, Inc. Report No. 10CFR21-0134, Rev. 0 - 10CFR21 Reporting of Defects and Non-Compliance - (Emo Cylinder Head with Fireface Thickness Below Specification Cylinder Head P/N 40121485) ML21096A1142021-04-0606 April 2021 Ametek Solidstate Controls - Updated Interim Notifcation ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19210D4342019-07-11011 July 2019 Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 ML19190A0432019-06-28028 June 2019 Discusses Proprietary Information for Curtiss-Wright SAS - 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML14042A2002014-01-21021 January 2014 Part 21 Report Regarding Non-Conformance of an Electrical Tubular Water Heater ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification IR 05000391/20130032013-08-21021 August 2013 Construction Deficiency Report 50-391/2013-03 - Failure to Implement Plant Changes - Final Report ML13240A0062013-08-21021 August 2013 Construction Deficiency Report 50-391/2013-03 - Failure to Implement Plant Changes - Final Report ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13094A1772013-03-18018 March 2013 Notice to the U.S. Nuclear Regulatory Commission of a Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters Manufactured by Aaf ML12326A7142012-11-21021 November 2012 Fourth Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries Lll and Lv ML12206A0552012-07-24024 July 2012 Second Interim Report Pursuant to 10 CFR 21 - Unexpected Degradation of Vital Batteries III and IV ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12061A2682012-02-28028 February 2012 Part 21 Report - Potential Minimum Wall Violation on Seismic Plate Valve Bodies ML11220A3492011-08-0505 August 2011 Notification of Potential Part 21 Potential Defect in Qualtech Np Safety Related Motor Control Center Buckets ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0520003332005-07-14014 July 2005 Part 21 Communication: Circuit Breaker Replacement Primary Bushings Not Tested to ANSI Standards ML0511602412005-04-14014 April 2005 Thermo Electron Svioc, SV18C and SV28C Series Recorders 2024-05-17
[Table view] Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) 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 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 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 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 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 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 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 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 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 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) 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 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 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO 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 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 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-024, 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-24-010, 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-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 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 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 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 August 21, 2013 CDR-50-391/2013-03 10 CFR 50.55(e)
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - CONSTRUCTION DEFICIENCY REPORT 50-391/2013 FAILURE TO IMPLEMENT PLANT CHANGES - FINAL REPORT
Reference:
TVA letter dated July 18, 2013, Watts Bar Nuclear Plant (WBN) Unit 2 - "Reply to Notice of Violation (EA-13-019) 391/2013611-01, -02, and -03 Related to TVA'S Commercial Grade Dedication Program" The purpose of this letter is to provide the final report for Construction Deficiency Report 391/2013-03 in accordance with 10 CFR 50.55(e) regarding a condition involving failure to implement plant changes. This condition represents a significant breakdown of a portion of the WBN Unit 2 Quality Assurance Program. TVA initially notified NRC of this deficiency on July 22, 2013, via Event Notification 49209.
TVA has performed evaluations for the systems where work had not been implemented and determined that the supports would have performed their safety function under normal operating and design basis loads had the additional work remained uncorrected. As a result of these evaluations, TVA has determined that no substantial safety hazards or impacts to safety-related systems, structures or components were identified regarding this issue.
TVA has completed actions to address the hardware and programmatic aspects of the identified conditions. Broader programmatic actions to address the significant breakdown in a portion of the WBN Unit 2 Quality Assurance Program were included in the above Reference.
U.S. Nuclear Regulatory Commission Page 2 August 21, 2013 There are no new commitments made in this letter.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 2 1 st day of August, 2013.
If you have any questions, please contact me at (423) 365-1260 or Gordon Arent at (423) 365-2004.
Respectfully, Raymond A. Hruby, Jr.
General Manager, Technical Services Watts Bar Unit 2
Enclosure:
Construction Deficiency Report 391/2013-03, Failure to Implement Plant Changes -
Final Report cc (Enclosure):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 REGARDING FAILURE TO IMPLEMENT PLANT CHANGES 10 CFR 50.55(e) - FINAL REPORT 391/2013-03 DESCRIPTION OF DEFICIENCY As a result of an extent of condition review for potential Quality Assurance breakdown issues in response to an apparent violation 05000391/2013611-02 related to TVA's Commercial Grade Dedication Program, TVA has identified a previous Problem Evaluation Report (PER) that constitutes a significant breakdown in a portion of the Quality Assurance program. This review was initiated upon discovery of a misinterpretation of 10 CFR 50.55(e), where it was thought that to be reportable a "significant breakdown in a portion of the Quality Assurance program" had to be associated with a confirmed substantial safety hazard.
The subject of the previous PER is as follows:
Previously, on May 31, 2011, TVA identified a number of revised Drawing Revision Authorizations (DRAs) that had not been incorporated into work orders to ensure field work required by the DRA revision was implemented in the field.
Specific problems initially identified were (1) Support 47A450-25-400 - Gaps shown in section A-A of DRA 52504-012 were not re-inspected.
(2) Support 47A450-25-403 - Dimensions showing the center anchor bolt location on section B-B of DRA 52504-047 were not re-inspected.
(3) Support 47A450-26 Size of shim plate shown on DRA 52574-011 was not re-inspected.
(4) Support 47A060-67-139 - Nut was not removed and anchor cut one thread above base plate as shown on DRA 52574-048 and QC re-inspection was not performed.
(5) Support 47A060-26 Size of shim plate shown on DRA 52574-053 was not re-inspected.
The above conditions were identified during the performance of Quality Assurance surveillance 25402-WBN-SR-1 1-1741.
This condition was documented as PER 378571. As a result of the above described review, TVA has concluded that a significant breakdown in a portion of the Quality Assurance program had occurred that could have produced a defect in a basic component. However, TVA has subsequently determined that no safety significance can be attributed to this condition. This issue has been resolved, and PER 378571 was closed on February 19, 2013.
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This condition is being reported in accordance with 10 CFR 50.55(e) as significant breakdown in a portion of the Quality Assurance program.
CAUSE OF THE DEFICIENCY The cause of the deficiency was determined to be Procedure 25402-000-GPP-0000-N3105, "Field Change Requests," was ambiguous in that it was not clear whether the current work order has to be revised or a new work order is to be issued for processing Field Change Requests (FCRs) approved with changes. The deficiencies were limited to support related FCRs.
SAFETY IMPLICATIONS Engineering has performed evaluations for the systems where work had not been implemented and determined that the supports would have performed their safety function under normal operating and design basis loads had the additional work remained uncorrected. These evaluations are also documented in closed PER 378571.
As a result of these evaluations, TVA has determined that no substantial safety hazards or impacts to safety-related systems, structures or components were identified regarding this issue.
CORRECTIVE ACTIONS Hardware Conditions/Extent of Condition For the five System 67 (Essential Raw Cooling Water) supports documented in the PER description above, Work Orders 112369678 (Items 1 and 2 above) and 112369534 (Items 3, 4, and 5) were initiated to address the deficiencies identified. These work orders have been completed.
This condition applies to WBN Unit 2 FCRs that have been approved with changes. TVA has reviewed those identified FCRs on System 67 and the remaining systems to identify changes that were not incorporated into a work order and implemented. To correct the identified issues found, TVA has initiated or revised work orders to implement the new scope of work if required. These actions are documented in closed PER 378571.
Engineering has performed an evaluation for each of the systems where work had not been implemented and determined that the supports would have performed their safety function under normal operating and design basis loads had the additional work remained uncorrected. These evaluations are also documented in closed PER 378571.
Procedure Revision TVA has revised Procedure 25402-000-GPP-0000-N3105 to include the steps outlined as follows:
For Field Change Requests (FCRs) that are to be "approved with changes", Design Engineering contacts the mechanical planning group to notify them that the FCR will be issued "approved with changes" prior to issuing the FCR. At the time of notification, E-2
Planning is to initiate a work order to implement the new work in the subject FCR and will provide the work order number to Engineering. Design Engineering will then reference the work order number in the FCR. Design Engineering will still coordinate the FCR with Field Engineering prior to issuance.
Specifically, Procedure 25402-000-GPP-0000-3105 was revised by modifying Section 6.2.2.d to state "If physical work is required, identify the work order number (or work order numbers) that will implement the FCR and (if applicable) the work order numbers that are affected by the change."
Training Training has been provided to the appropriate Field Engineers, planners and Design Engineering personnel on the revised procedure requirements regarding processing FCRs approved with changes.
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