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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc 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 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 ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve 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 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 2024-06-23
[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 ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve 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 ML14192A0382014-07-0303 July 2014 Part 21 Report Incorrect Industrial Irradiator ML14192A0402014-07-0303 July 2014 Interim Report - 10CFR Part 21 Evaluation Regarding Potential Deficiencies 2023-12-14
[Table view] Category:Letter
MONTHYEARML24289A1232024-10-24024 October 2024 Letter to James Barstow Re Environmental Scoping Summary Report for Browns Ferry 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 CNL-24-077, Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 12024-10-0909 October 2024 Application for Subsequent Renewed Operating Licenses, Response to Request for Additional Information, Set 1 ML24270A2162024-09-27027 September 2024 Notice of Intentions Regarding Preliminary Finding from NRC Inspection Report 05000260/2024090, EA-24-075 ML24262A1502024-09-24024 September 2024 Requalification Program Inspection - Browns Ferry Nuclear Plant 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 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 ML24263A2952024-09-19019 September 2024 Site Emergency Plan Implementing Procedure Revision 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 IR 05000260/20240902024-09-17017 September 2024 NRC Inspection Report 05000260/2024090 and Preliminary White Finding and Apparent Violation - 1 CNL-24-062, Cycle 16 Reload Analysis Report2024-09-16016 September 2024 Cycle 16 Reload Analysis Report ML24255A8862024-09-10010 September 2024 Core Operating Limits Report for Cycle 16 Operation, Revision 0 ML24239A3332024-09-0303 September 2024 Full Audit Plan IR 05000259/20244042024-09-0303 September 2024 Cyber Security Inspection Report 05000259/2024404 and 05000260-2024404 and 05000296/2024404-Cover Letter IR 05000259/20240052024-08-26026 August 2024 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2024005, 05000260/2024005 and 05000296/2024005 ML24225A1682024-08-16016 August 2024 – Notification of Inspection and Request ML24219A0272024-08-0606 August 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations IR 05000259/20244022024-08-0606 August 2024 Security Baseline Inspection Report 05000259/2024402 and 05000260/2024402 and 05000296/2024402 IR 05000259/20240022024-08-0202 August 2024 Brown Ferry Nuclear Plant – Integrated Inspection Report05000259/2024002 and 05000260/2024002 and 05000296/2024002 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 ML24183A4142024-07-10010 July 2024 – License Renewal Regulatory Limited Scope Audit Regarding the Environmental Review of the License Renewal Application (EPID Number: L-2024-SLE-0000) (Docket Numbers: 50-259, 50-260, and 50-296) ML24190A1292024-07-0808 July 2024 Main Steam Relief Valves Lift Settings Outside of Technical Specifications Required Setpoints ML24185A1512024-07-0303 July 2024 Inoperability of Unit 3 Diesel Generator Due to Relay Failure ML24184A1142024-07-0202 July 2024 Site Emergency Plan Implementing Procedure Revision ML24183A3842024-07-0101 July 2024 Registration of Use of Cask to Store Spent Fuel (MPC-364, -365) ML24179A0282024-06-26026 June 2024 Evaluation of Effects of Out-of-Limits Condition as Described in IWB-3720(a) ML24176A1022024-06-24024 June 2024 Reactor Scram Due to Generator Step-Up Transformer Failure ML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24176A1132024-06-23023 June 2024 American Society of Mechanical Engineers, Section XI, Fourth 10 Year Inspection Interval, Inservice Inspection, System Pressure Test, Containment Inspection, and Repair and Replacement Programs, Owner’S Activity Report Cycle 21 Oper 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) ML24155A0042024-06-18018 June 2024 Proposed Alternative to the Requirements of the ASME Code (Revised Alternative Request 0-ISI-47) ML24158A5312024-06-0606 June 2024 Registration of Use of Cask to Store Spent Fuel (MPC-361, -362, -363) ML24071A0292024-06-0505 June 2024 Subsequent License Renewal Application Enclosure 3 - Proprietary Determination Letter ML24068A2612024-06-0505 June 2024 SLRA Fluence Methodology Report - Proprietary Determination Letter IR 05000259/20244032024-05-22022 May 2024 – Security Baseline Report 05000259/2024403 and 05000260/2024403 and 05000296/2024403 ML24141A2462024-05-20020 May 2024 High Pressure Coolant Injection Inoperable Due to Rupture Disc Failure and Resulting System Isolation ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24136A0702024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000259/20240012024-05-14014 May 2024 Integrated Inspection Report 05000259/2024001, 05000260/2024001, and 05000296/2024001 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 ML24123A2012024-05-0202 May 2024 NRC Cybersecurity Baseline Inspection (NRC Inspection Report 05000259/2024404, 05000260-2024404, 05000296/2024404) and Request for Information ML24122A6852024-05-0101 May 2024 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual CNL-24-036, – 10 CFR 50.46 Annual Report2024-04-25025 April 2024 – 10 CFR 50.46 Annual Report ML24116A2522024-04-25025 April 2024 Site Emergency Plan Implementing Procedure Revision ML24115A1652024-04-24024 April 2024 Breaker Trip Automatically Started an Emergency Diesel Generator 05000296/LER-2024-001, Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup2024-04-22022 April 2024 Primary Containment Isolation Valve Inoperable Due to Incorrect Motor Operated Valve Setup 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 ML24087A2302024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting 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 2024-09-03
[Table view] |
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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