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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML22075A2192021-11-29029 November 2021 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0133, Rev. 0 - Swing Check Valve, P/N ESl50359 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 ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML17114A0692017-04-19019 April 2017 Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML15223B2662015-08-0707 August 2015 Part 21 Report - Crane Nuclear Pressure Seal Valve with Retaining Rings ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML14309A5292014-10-31031 October 2014 Closure of 10 CFR Part 21 Interim Report - Engine Systems, Inc., Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14318A1962014-09-0505 September 2014 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14216A3772014-07-30030 July 2014 Part 21 Report - Incorrect Industrial Irradiator Dose ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14189A4172014-07-0707 July 2014 Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator ML14192A0382014-07-0303 July 2014 Part 21 Report Incorrect Industrial Irradiator ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14069A4672014-02-26026 February 2014 Part 21 Report Involving a Potential Manufacturing Defect in Replacement Masterpact Cradles ML13260A0772013-09-12012 September 2013 10 CFR Part 21 Interim Report - General Electric (GE) Hitachi Nuclear Energy - Sbm Type Manual Switch ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification 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 ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML13008A3212013-01-0404 January 2013 Anti-Rotation Pin Failure in Anchor Darling (Flowserve) Double Disc Gate Valve ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1025201572010-08-16016 August 2010 Initial Exam 2010-301 Final Administrative Documents ML1018907392010-07-0101 July 2010 Part 21 Report Concerning Failure of Turbine Overspeed Reset Control Valve Diaphragm ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0511602412005-04-14014 April 2005 Thermo Electron Svioc, SV18C and SV28C Series Recorders ML0506302442005-03-0202 March 2005 Part 21 Report Concerning MCPR Limits and MCPR Monitoring ML0501902562005-01-14014 January 2005 Non-Emergency Event Report from Framatome Anp, Inc ML0232901622002-11-18018 November 2002 Final Report, Stability Option III: Possible Successive Confirmation Count Resets - Not Reportable 2024-01-23
[Table view] Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML22208A0042022-06-17017 June 2022 Nutherm International, Inc., USNRC 10CFR Part 21 Notification Reference: Arnold Magnetics Power Supply Part Number PBM-24-106 ML22153A0792022-04-0707 April 2022 10CFR Part 21 Notification for Curtiss-Wright Supplied RCS-Dresser Actuator P/N: SURE-24-10-4 ML21294A0292021-10-0404 October 2021 Flowserve Part 21 Notification for Limitorque Supplied DC Motor 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 ML19002A2042018-12-21021 December 2018 to Engine Systems, Inc., Part 21 Report Re Emd Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18341A2472018-12-0606 December 2018 Mirion Technologies - 10 CFR Part 21.21 Report Re Relays Defect ML18354A7422018-12-0404 December 2018 Engine Systems, Inc., Submittal of 1OCFR21 Reporting of Defects and Non-Compliance - Report No. 1OCFR21-0123, Rev. 0 - Emo Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18087A0032018-03-21021 March 2018 Crane Nuclear, Inc. - Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve (Updated) ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML18079A0142018-03-0606 March 2018 Crane Nuclear, Inc., 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl I0x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML18003A2602017-12-19019 December 2017 Crane Nuclear, Inc. - 10 CFR Part 21 Notification of Defect on Weak Link Analysis for Chapman Gate Valve Figure L900, Item #18, Drawing CC05307, Revision B ML17194A8252017-07-11011 July 2017 Part 21 Report Re Wedge Pin Failure in Anchor Darling Motor Operated Double Disc Gate Valves with Threaded Stem to Upper Wedge Connections ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML17114A0692017-04-19019 April 2017 Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16278A4712016-09-22022 September 2016 Notification of 10 CFR Part 21 Condition, Masterpact Breaker Fail to Close ML16281A2702016-09-22022 September 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML16243A4742016-08-26026 August 2016 Potential Part 21 Unqualified Component in Certain Allen Bradley Timing Relays ML16238A1862016-08-15015 August 2016 Update - Report of Potential l0CFR Part 21, Allen Bradley Timing Relay Model 700RTC-NRC Event Number 51030, Accession Number ML15134A016 ML16232A6042016-08-15015 August 2016 Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML16196A0642016-07-10010 July 2016 Part 21 Report - Materials Not Properly Dedicated ML16188A3742016-06-30030 June 2016 Part 21 - Inadequate Swaging and Adherence of Silicone O-Ring and Silicone PAD Soft Seat Main Disc and Pilot Disc Assemblies ML16154A2072016-05-26026 May 2016 Part 21, Azz/Nli Nuclear Logistics, Inc., Potentially Unqualified Component in Certain Allen Bradley Timing Relays Model 700RTC ML16194A1992016-05-25025 May 2016 Azz/Nli - Update - Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML16111A4202016-04-0808 April 2016 Part 21 Report No. P21-04302015, Rev. 1 Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays, Per Browns Ferry, Ginna, Millstone, Nine Mile Point, North Anna, Ft. Calhoun, Perry, River Bend, South Texas Project ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML15159A5682015-04-30030 April 2015 Report of Potential 10CFR Part 21, Allen Bradley Timing Relay Model 700RTC ML15099A0422015-04-0202 April 2015 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML15099A0432015-04-0202 April 2015 Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches ML14303A2582014-10-27027 October 2014 10 CFR Part 21 Notification of an Error in Powerplex MCPR and LHGR Limit Input for Browns Ferry, Unit 2 ML14274A0522014-09-22022 September 2014 Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities ML14318A1962014-09-0505 September 2014 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14216A3772014-07-30030 July 2014 Part 21 Report - Incorrect Industrial Irradiator Dose ML14220A0212014-07-29029 July 2014 Final Report - Closure for Iterim 10CFR Part 21 Report (PMT No. 14-01, Ncr Event No. /Accession No. ML14192A040) ML14213A0992014-07-24024 July 2014 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14189A4172014-07-0707 July 2014 Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator ML14192A0402014-07-0303 July 2014 Interim Report - 10CFR Part 21 Evaluation Regarding Potential Deficiencies ML14192A0382014-07-0303 July 2014 Part 21 Report Incorrect Industrial Irradiator 2023-12-14
[Table view] Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump 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 ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions 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 ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 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 ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 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 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 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 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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Dz5~cJ ie4c(j cbrAqm It[ICA Tennessee Valley Authority, Post Office Box 2000. Decatur, Alabama 35609-2000 September 5, 2014 10 CFR 21.21 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, NRC Docket Nos. 50-259, 50-260, and 50-296 DPR-52, and DPR-68
Subject:
10 CFR Part 21 Interim Report -Engine Systems, Inc. -Emergency Diesel Generator Heat Exchanger CEY564L-HEX The Tennessee Valley Authority (TVA) recently identified a leak in the weld of the Emergency Equipment Cooling Water outlet piping on the head of the C2 Emergency Diesel Generator (EDG) heat exchanger, CEY564L-HEX.
Corrective Action Program documents were written to document the failure of the heat exchanger weld and to perform an engineering evaluation of the condition.
TVA's evaluation concluded that this condition has the potential to constitute a reportable condition pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 21, "Reporting of Defects and Noncompliance," and as such, requires additional evaluation.
The TVA must perform additional analysis in order to determine the significance of the weld defect. TVA will submit a final 10 CFR Part 21 report by November 6, 2014. The enclosure to this letter provides information required by 10 CFR Part 21.21 (a)(2) for the interim report of this condition.
There are no new regulatory commitments contained in this letter. Should you have any questions concerning this submittal, please contact J. L. Paul, Nuclear Site Licensing Manager, at (256) 729-2636.Respectfully S-/E3r U.S, Nuclear Regulatory Commission Page 2 September 5, 2014
Enclosure:
10 CFR Part 21 Interim Report -Engine Systems, Inc. -Emergency Diesel Generator Heat Exchanger CEY564L-HEX cc (w/ Enclosure):
NRC Regional Administrator
-Region II NRC Senior Resident Inspector
-Browns Ferry Nuclear Plant Enclosure Browns Ferry Nuclear Plant, Units 1, 2, and 3 10 CFR Part 21 Interim Report Engine Systems, Inc. -Emergency Diesel Generator Heat Exchanger CEY564L-HEX See Enclosed 10 CFR Part 21 Interim Report -Engine Systems, Inc. -Emergency Diesel Generator Heat Exchanger CEY564L-HEX Name and Address of the Individual Making the Interim Report Mr. K. J. Poison Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Post Office Box 2000 Decatur, Alabama 35609-2000 Identification of the facility, the activity, or basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect (under evaluation)
On July 10, 2013, the Tennessee Valley Authority (TVA) identified a leak in the weld of the Emergency Equipment Cooling Water (EECW) outlet piping on the head of the C2 Emergency Diesel Generator (EDG) heat exchanger, CEY564L-HEX.
Identification of the firm constructin-g the facility or supplying the basic component which fails to comply or contains a defect (under evaluation)
Engine Systems, Inc.175 Freight Rd Rocky Mount, NC 27804 Description of the Deviation or Failure to Comply that is being Evaluated A leak was identified in the weld of the EECW outlet piping on the head of the C2 EDG heat exchanger.
The TVA determined the cause of the leak to be a vendor manufactured failed weld in the weld joint between the EECW line connection and the inlet / outlet heat exchanger head.Evaluation Status The TVA determined the cause of the leak to be a vendor manufactured failed weld in the weld joint between the EECW line connection and the inlet / outlet heat exchanger head. The C2 EDG heat exchanger will undergo additional analysis in order to determine the safety significance of the weld defect. Once the analysis is complete, TVA will complete the 10 CFR Part 21 evaluation.
Date on which Evaluation will be Completed The TVA will submit a final 10 CFR Part 21 report by November 6, 2014.E-1
,NSTRUCTIONS FOR FORM 41L LICENSING TRANSMITTAL TO NRC
SUMMARY
AND CONCURRENCE SHEET DATE DUE: September 5, 2014 -(A) PREPARER:
Mark B. Acker (7533)
SUBJECT:
Interim Part 21 Report -C2 Emergency Diesel Generator Heat Exchanger Weld Defect -PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation nl YES 0 NO (E) Posting Requirements Ii YES 0 NO (C) Licensing Verification 0 YES El NO (F) FSAR EFFECT El YES 0 NO (D) New Commitments E] YES Z NO (G) OGC Consultation El YES 0 NO (H) LIC-109 Review El YES 0 N/A (I) Engineering Independent El YES 0 NO Technical Review (ITR)*Engineering (only): I Design Change # N/A INDEPENDENT TECHNICAL REVWER (J) Licensing (only): PEER CHECKER CONCURRENCE (K)A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.NAME ORGANIZATION SIGNATURE DATE ICAREB26 J. Paul Site Licensing Manager V<<.,'I S. Hunnewell Engineering Manager I/P. Summers Director Plant Support B. Wetzel Corp Licensing 0 (L) Licensing (only): S>--J(k&{ ,L -"'5rO .)QUALITY IEVIEWER TVA 41035 Page 1 of 1 NPG-SPP-03.10-1
[10-31-2013]
,NSTRUCTIONS FOR FORM 41 LICENSING TRANSMITTAL TO NRC
SUMMARY
AND CONCURRENCE SHEET DATE DUE September
- 5. 2014 (A) PREPARER Mark B. Acker (7533)SUBJECT Interim Part 21 Report -C2 Emergency Diesel Generator Heat Exchanger Weld Defect -PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation E YES & NO (E) Posting Requirements E YES 0 NO (C) Licensing Verification 09 YES C] NO (F) FSAR EFFECT LI YES 0 NO (D) New Commitments 0 YES Z NO (G) OGC Consultation f- YES 0 NO (H) LIC-109 Review C3 YES [D N/A (I) Engineering Independent C] YES 0 NO Technical Review (ITR)*Engineering (only) Design Change # N/A INDEPENDENT TECHNICAL REVIWER (j) Licensing (only) -.C/ 74) 6?PEER CHECKER CONCURRENCE (K)A concurrence signature reflects that the signatory has assured that. with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy. the submittal is complete and accurate, applicable commttments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared NAME ORGANIZATION SIGNATURE DATE ICA REB .7~a.L-- _____.1. uinul Site Liccnsingf Nlanag~er S. IlunnewelI Enginecrint!
Manager 1'. S.ummers Director Plant Support 11. Wetzel Corp Licenring (L) Licensing (only).QUALITY REVIEWER TVA 41035 Page 1 of 1 NPG-SPP-03 10-1 110-31-20131 oNSTRUCTIONS FOR FORM 41L LICENSING TRANSMITTAL TO NRC
SUMMARY
AND CONCURRENCE SHEET DATEDUE Setembr 5 204 I(A) PREPARER:
Mark B. Acker (7533)
SUBJECT:
Interim Part 21 Report -C2 Emergency Diesel Generator Heat Exchanger Weld Defect -PER 913911 REGULATORY CONSIDERATIONS (B) Oath or Affirmation
[]YES 0 NO (E) Posting Requirements El YES 0 NO (C) Licensing Verification
[ YES El NO (F) FSAR EFFECT []YES [ NO (D) New Commitments
[] YES [ NO (G) OGC Consultation El YES [] NO (H) LIC-109 Review E] YES Z N/A (I) Engineering Independent El YES
- NO Technical Review (ITR)*Engineering (only): / Design Change # NIA INDEPENDENT TECHNICAL REWER (J) Licensing (only): A/5 PEER CHECKER CONCURRENCE (K)A concurrence signature reflects that the signatory has assured that, with respect to the signatory's area of cognizance, the submittal is appropriate and consistent with TVA Policy, the submittal is complete and accurate, applicable commitments are approved for implementation and supporting documentation for submittal completeness and accuracy has been prepared.NAME ORGANIZATION SIGNATURE DATE ICAREB J. Paul Site Licensing Manager S. Hunnewell Engineering Manager .P. Summers Director Plant Support B. Wetzel Corp Licensing (L) Licensing (only): /QUALITY REVIEWER TVA 41035 Page 1 of 1 4NPG-SPP-03.10-1
[10-31-20131 Integrated Coi., 1 leteness and Accuracy Review L..:,uation Board Minutes 01 /,o5 /iohi Date: Subject mm/dd/yyyy ,T')vt e, ,r% 2 ýI A eo, f- -P, C2 Lb6 H,) L1e/J l)e bec.ýCorrespondence Type: NOV Response E] GL Response E] Bulletin Response [] CAL Response 5]Allegation Response El RAI Response [I NOED [] Relief Request 0 Security Event Report 5 LAR 0 LER El Licensedclperator
] Required Report 0 Other'q Describe:
Tot I 'I r", -pp -Board Members Member Name (print) Title Chairperson
-- ; j-'vl Pv1-e,,-Member #2 C/\ ne A essar Member #3 ";~ ;ce- ~L~;ce~Member #4_(if necessary)
__________________________
Minutes Discussion of Validation/Verification Performed-., fJ ÷j
-do 5----j due i-J e, f\ 1r1e-f,"nly n(J ý F er 9 e-r-\Yes*j)I p.Cý n evcA /U dC, , ý"C Conclusion Additional Validation/Verification Required: Now'Yesl1 Describe Additional Validation (if required):
C1. Q LC L A/ CV;./(6 e Icc/y %dr--eci CN~2&Ji Minutes Approved:/ Q J ICAREB Chairperson/Date