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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23066A2212023-03-0707 March 2023 Velan, Inc. - Revised Part 21 Notification Re Butterfly Valves Found to Have a Number of Fasteners Loose ML22303A0042022-08-31031 August 2022 Final Report Notification Pursuant to 10 CFR Part 21.21, Regarding Supply of 6 NPS Sch. 40 Seamless Stainless-Steel Pipe; Manufacturer: Maxim Tubes Company Pvt. Ltd.; Heat No: N200309AW01, SR No: 7; 9 Pcs; 180 Feet Total Procured as Unquali ML22259A1732022-08-26026 August 2022 EN 55960 - Curtiss Wright Part 21 Report Re Potential Defect in Configuration of the Quick Disconnect Connector Cable Assemblies Supplied to McGuire and Catawba Nuclear Power Stations ML22201A1012022-07-18018 July 2022 Framatome, Inc. - 10 CFR Part 21 Notification of Existence of a Defect and Failure to Comply ML22222A0092022-07-0101 July 2022 EN 55974 - Flowserve, Part 21 Report Re Solenoid Coil Failure of Model 38878-8 Solenoid Valve at Catawba Nuclear Station for Use on FWIV Actuator RA-22-0127, Interim Part 21 Report of a Deviation or Failure to Comply for Cutler-Hammer Relay2022-04-0808 April 2022 Interim Part 21 Report of a Deviation or Failure to Comply for Cutler-Hammer Relay ML20073G4572020-03-0909 March 2020 Carrier Corporation - Final Report Notification of Defect Pursuant to 10 CFR Part 21 for 17FA999-1200-107 Oil Pump ML20024D8232020-01-10010 January 2020 Carrier Corp., Interim Report/Notification of Defect Pursuant to 10 CFR Part 21 ML20016A2202020-01-10010 January 2020 Carrier - Interim Report/Notification of Defect Pursuant to 10 CFR Part 21 ML19346H8732019-12-12012 December 2019 Westinghouse Electric Company - Notification of the Potential Existence of Defect Pursuant to 10 CFR Part 21 ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML18302A2282018-10-19019 October 2018 Itt Enidine - USNRC 10CFR Part 21 Notification ML18269A1122018-09-12012 September 2018 Engine Systems, Inc. Report No. 10CFR21-0122, Rev. 0 - 10CFR21 Reporting of Defects and Non-Compliance 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 ML17173A1392017-06-0909 June 2017 Engine Systems, Inc. - Transmittal of 10CFR21 Reporting of Defects and Non-Compliance - Report No. 10CFR21-0117, Rev. 0 ML17165A4072017-06-0909 June 2017 Part 21 Report - Defective Motor Operated Potentiometer ML16328A3102016-11-18018 November 2016 Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 MNS-16-078, Written Notification Joslyn Clark Overload Heater Element Part No. 24552016-10-19019 October 2016 Written Notification Joslyn Clark Overload Heater Element Part No. 2455 ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16281A2712016-09-30030 September 2016 Part 21 - Safety Related Component Welding by an Unqualified Welder 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 ML16281A2722016-09-19019 September 2016 Part 21 Notification - Joslyn Clark Overload Heater Element Part Number 2455 ML16243A4752016-08-26026 August 2016 Part 21 Safety Related Component Welding by an Unqualified Welder ML16209A0502016-07-13013 July 2016 Part 21 - Furmanite Nuclear Grade Leak Seal Material FSC-N-1B ML16196A0642016-07-10010 July 2016 Part 21 Report - Materials Not Properly Dedicated ML16139A8322016-05-13013 May 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16139A8332016-05-13013 May 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16127A5952016-05-0404 May 2016 Rotork Controls Inc. Part 21 Notification Concerning V12 (Pt No. N69-921) and K5 (N69-838 & N69-926) Safety Related Micro Switches ML16258A4562015-11-0505 November 2015 Part-21 Report - Closed Switch Not Actuating When Valve Is Fully Closed ML15303A0062015-10-26026 October 2015 Part 21 Report Regarding Closed Switch No. Actuating When Valve Is Fully Closed, Per Catawba Nuclear Station ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring ML15049A4582015-02-0606 February 2015 Thermo Gamma-Metrics, LLC - Part 21 Report Regarding Shutdown Margin Monitor Environmental Qualification Noncompliance ML14094A4452014-04-0101 April 2014 Notification of Part 21 Report on Defective Raw Material Used to Manufacture Valve Stems ML14085A0122014-03-21021 March 2014 Notification of Part 21 - Sbm Selector Switches Contact Assembly Unplanned Manufacturing Change ML13284A0842013-10-0303 October 2013 Deficiency Report from Baldor Electric Co., on Nuclear Nonconformance Event No. 49302 ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13102A3032013-04-10010 April 2013 Part 21 Involving a Potential Weld Defect ML13099A0932013-04-0505 April 2013 Part 21 Report of Limitorque Valves with Incorrect Motor Nameplates Installed ML13079A3202013-03-18018 March 2013 Notification of Potential Part 21 Interim Report Re Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12356A3022012-11-27027 November 2012 Notification of Potential Part 21 Report Involving Performance of Npt Stamped Cavitrol III Plugs at Catawba Nuclear Station ML12318A0412012-11-0808 November 2012 Part 21 Report - Commercial Grade Dedication Not Properly Applied to Butterfly Valves ML12219A2312012-08-0303 August 2012 Us NRC 10CFR Part 21 Notification from Flowserve on Seal Cap for Kerotest 3/4, 1, 1-1/2, and 2 Y-Type Globe Valves 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 2023-07-14
[Table view] Category:Letter
MONTHYEARIR 05000369/20240032024-11-0404 November 2024 Integrated Inspection Report 05000369/2024003 and 05000370/2024003 IR 05000413/20240032024-11-0404 November 2024 Integrated Inspection Report 05000413/2024003 and 05000414/2024003 ML24303A4212024-10-30030 October 2024 Mcguire Nuclear Station, Units 1 & 2, Notification of an NRC Fire Protection Team Inspection FPTI NRC 05000369/2025010, 05000370/2025010 and Request for Information RFI ML24297A6222024-10-11011 October 2024 PCA Letter to NRC Catawba Hurricane Helene IR 05000369/20244022024-10-0808 October 2024 Security Baseline Inspection Report 05000369/2024402 05000370/2024402 IR 05000413/20240112024-10-0101 October 2024 Biennial Problem Identification and Resolution Inspection Report 05000413/2024011 and 05000414/2024011 ML24255A8312024-09-23023 September 2024 Project Manager Assignment ML24261B9782024-09-19019 September 2024 Notification of an NRC Fire Protection Team Inspection NRC Inspection Report 05000413-2024010, 05000414-2024010 and Request for Information IR 05000414/20240912024-09-0505 September 2024 Final Significance Determination of a White Finding and Nov and Assessment Followup Letter-NRC Inspection Report 05000414-2024091 IR 05000413/20240052024-08-26026 August 2024 Updated Inspection Plan for Catawba Nuclear Station (Report 05000413/2024005 & 05000414/2024005) IR 05000369/20240052024-08-26026 August 2024 Updated Inspection Plan for McGuire Nuclear Station, Units 1 and 2, (Report 05000369-2024005 and 05000370-2024005) ML24235A1542024-08-22022 August 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000413-2024402 and 05000414-2024402) IR 05000413/20240022024-08-0808 August 2024 Integrated Inspection Report 05000413-2024002 and 05000414-2024002 and Apparent Violation IR 05000413/20244032024-08-0101 August 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000413/2024403; 05000414/2024403 IR 05000369/20244042024-08-0101 August 2024 Cover Letter Security Baseline Inspection Report 05000369/2024404 and 05000370/2024404 IR 05000369/20253012024-07-29029 July 2024 Notification of Licensed Operator Initial Examination 05000369/2025301 and 05000370/2025301 IR 05000369/20244032024-07-25025 July 2024 – Cyber Security Inspection Report 05000369/2024403 and 05000370/2024403 Rev IR 05000369/20240022024-07-24024 July 2024 Integrated Inspection Report 05000369/2024002 and 05000370/2024002 ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000369/20244012024-07-0303 July 2024 – Security Baseline Inspection Report 05000369/2024401 and 05000370/2024401 ML24176A2802024-06-26026 June 2024 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000369-2024404 and 05000370-2024404) ML24178A0552024-06-26026 June 2024 Requalification Program Inspection – Catawba Nuclear Station IR 05000414/20240902024-06-24024 June 2024 NRC Inspection Report 05000414/2024090 and Preliminary White Finding and Apparent Violation ML24170A8632024-06-11011 June 2024 Flowserve June 11, 2024, Part 21 Notification - Redacted Version for Publishing IR 05000369/20240112024-06-0404 June 2024 Biennial Problem Identification and Resolution Inspection Report 05000369/2024011 and 05000370/2024011 ML24144A1162024-05-28028 May 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24149A1772024-05-28028 May 2024 NRC Response to Duke Energy 2025 FOF Schedule Change Request (Catawba and McGuire) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000413/20240012024-05-10010 May 2024 Integrated Inspection Report 05000413/2024001 and 05000414/2024001 and Apparent Violation IR 05000369/20240012024-05-0808 May 2024 Integrated Inspection Report 05000369-2024001 and 05000370-2024001 and 07200038-2024001 ML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf ML24100A8742024-04-10010 April 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000369/2024403; and 05000370/2024403 ML24052A3062024-04-0808 April 2024 Issuance of Amendment Nos. 331 & 310, Regarding Adoption of Title 10 of Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24095A1072024-04-0808 April 2024 – Review of the Spring 2023 Steam Generator Tube Inspection Report (C1R27) ML24031A5402024-03-26026 March 2024 Issuance of Amendment Nos. 330 and 309 Regarding Implementation of TSTF 505,Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B ML24085A2402024-03-21021 March 2024 Requalification Program Inspection - McGuire Nuclear Station IR 05000413/20243012024-03-12012 March 2024 – Notification of Licensed Operator Initial Examination 05000413/2024301 and 05000414/2024301 ML24017A0652024-03-0808 March 2024 Issuance of Amendment Nos. 319 and 315 to Technical Specification 3.7.11, Control Room Area Chill Water System (Cracws) 05000414/LER-2024-001, Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan2024-03-0404 March 2024 Condition Prohibited by Technical Specifications and Loss of Safety Function Due to Failed Damper Controller for the 2A1 Emergency Diesel Generator Room Ventilation Fan IR 05000413/20230062024-02-28028 February 2024 Annual Assessment Letter for Catawba Nuclear Station Units 1 and 2 - (NRC Inspection Report 05000413/2023006 and 05000414/2023006) IR 05000369/20230062024-02-28028 February 2024 Annual Assessment Letter for McGuire Nuclear Station, Units 1 and 2 - NRC Inspection Report 05000369/2023006 and 05000370/2023006 ML24024A2182024-02-0505 February 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000413/20230042024-02-0202 February 2024 – Integrated Inspection Report 05000413-2023004 and 05000414-2023004 IR 05000369/20230042024-01-31031 January 2024 Integrated Inspection Report 05000369/2023004 and 05000370/2023004 ML24005A2512024-01-26026 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24019A1392024-01-25025 January 2024 TSTF 505 and 50.69 Audit Summary ML24019A2002024-01-24024 January 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000369/20234022023-12-14014 December 2023 – Material Control and Accounting Program Inspection Report 05000369/2023402 and 05000370/2023402 05000369/LER-1923-001, Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error2023-12-13013 December 2023 Automatic Actuation of the 1A Motor Driven Auxiliary Feedwater Pump Due to Human Error ML23317A2272023-11-17017 November 2023 William B. McGuire Nuclear Station, Units 1 and 2 - Transmittal of Dam Inspection Report - Non-Proprietary 2024-09-05
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Duke JAMES R. MORRIS ahEnergy Vice President Duke Energy Corporation Catawba Nuclear Station 4800 Concord Road York, SC 29745 803-701-4251 803-701-3221 fax February 22, 2011 10 CFR 21.21 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC (Duke Energy)Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413 and 50-414 McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 10 CFR 21 Notification
-Identification of Defect Pursuant to 10 CFR 21.21(d)(3)(ii), Duke Energy is providing the required written notification of the identification of a defect. This information was initially reported to the NRC Operations Center on January 24, 2011 (Event Number 46568).The attachment to this letter provides the information required by 10 CFR 21.21. In addition, the attachment discusses the relevance of this issue to Duke Energy's Catawba and McGuire Nuclear Stations.
There are no commitments contained in this letter or its attachment.
Should you have any questions or require additional information, please contact L.J. Rudy at (803) 701-3084.Very truly yours, James R. Morris LJR/s Attachment www. duke-energy, com Document Control Desk Page 2 February 22, 2011 xc (with attachment):
V.M. McCree Regional Administrator U.S. Nuclear Regulatory Commission
-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J.H. Thompson (addressee only)NRC Project Manager U.S. Nuclear Regulatory Commission Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 G.A. Hutto, III NRC Senior Resident Inspector Catawba Nuclear Station J.B. Brady NRC Senior Resident Inspector McGuire Nuclear Station ATTACHMENT 10 CFR 21.21 NOTIFICATION 600 VOLT ESSENTIAL AUXILIARY POWER SYSTEM MOTOR CONTROL CENTER STAB ASSEMBLIES This notification follows the format of and addresses the considerations contained in 10 CFR 21.21 (d)(4)(i)-(viii).(i) Name and address of the individual or individuals informing the Commission:
James R. Morris, Vice President Catawba Nuclear Station 4800 Concord Road York, SC 29745 (This individual is informing the Commission for both Catawba and McGuire.)(ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect: The basic component which is the subject of this notification is a stab assembly (sometimes known as a disconnect), purchased commercial grade and dedicated by Duke Energy for use in nuclear safety related applications.
Specific stab assembly information is as follows: The specific part is a stab assembly for connecting motor control center feeder circuits to the motor control center main bus.(iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect: The affected stab assemblies were supplied by Electrical Power Systems, Inc. (EPSI).(iv) Nature of the defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply: Backaround The Catawba and McGuire 600 volt Essential Auxiliary Power System motor control centers were originally supplied by Nelson Electric under a 10 CFR 50 Appendix B quality assurance program. The motor control centers were custom engineered for Duke Energy. The Nelson Electric design document describing the stab assemblies is drawing BA-2335, "Stab Assembly For W Moulding" (Nelson Electric Drawing).
During the 1990s, EPSI began to supply parts for these motor control centers. However, EPSI did not maintain a 10 CFR 50 Appendix B quality assurance program. Subsequently, Duke Energy decided to procure the stab assemblies from EPSI as commercial grade equipment and dedicate them for use in nuclear safety related applications.
In 1998, Duke Energy established commercial grade document number CGD-3014.04-05-0002,"Motor Control Center Plug In Unit Stab Assemblies" for these stab assemblies.
This document includes a sketch of the stab assemblies which contains the same detail as found on the Nelson Electric Drawing.1 Event Description In 2006, Catawba ordered stab assemblies under Duke Energy catalog ID 456194. One of the affected stab assemblies was installed at Catawba on June 3, 2010 in the circuit for the Diesel Generator (DG) I B jacket water keep warm pump motor. The stab assembly failed on June 5, 2010. Following the failure, DG 1B jacket water temperature began to decrease.
The DG was started and run for a period of time to maintain temperature in the required range.It was subsequently discovered that the Z-phase wiring between the breaker and the bus stab was not connected (i.e., the Z-phase bus stab was totally disconnected from the Z-phase wiring to the breaker) in the associated motor control center compartment.
The X-phase and Y-phase bus stabs and wiring remained connected to the breaker as designed.
The failure of this stab assembly resulted in the loss of the Z-phase feed to the motor, electrical arcing inside the motor control center compartment, and a failed pump motor due to single-phasing the motor.After the failure, Duke Energy received information showing that EPSI had revised the drawing referenced in CGD-3014.04-05-0002 and changed the method of connecting the wires to the stabs. The original Nelson Electric Drawing specified a welded connection, with many details. The EPSI amended drawing specified a soldered butt connection.
The Duke Energy Metallurgical Laboratory evaluated the failed stab assembly.
This evaluation showed that in addition to a less substantial method of attachment, there were disconnected wire strands, signs of overheating, and excess solder flux leading to oxidation and corrosion.
It was concluded that the DG I B jacket water keep warm pump motor failed due to inadequate connection of the wires to the stab assembly.
During parts dedication, the new stab assemblies passed basic electrical checks, but there was no visual inspection of the soldering because the connections had been inserted into the stab assembly molding.The affected stab assemblies were not utilized in any other nuclear safety related application at Catawba and they were not utilized in any nuclear safety related application at McGuire. However, they could have been; therefore, the safety hazard which could have been created would have depended upon the exact application in which they could have been utilized.
Catawba and McGuire determined that the theoretical worst case nuclear safety impact would have been a failure of valve NV252A (Catawba) and NV221A (McGuire) (Centrifugal Charging Pump Suction from Refueling Water Storage Tank) to open following a design basis accident requiring Emergency Core Cooling System (ECCS) actuation.
Failure of this valve to open would have rendered Train A of the ECCS inoperable.(v) The date on which the information of such defect or failure to comply was obtained: Following internal technical evaluation and discussion with EPSI, Duke Energy performed the evaluations required by 10 CFR 21 and Duke Energy procedures and determined that this issue is 10 CFR 21 reportable on January 20, 2011. The responsible company officers were formally notified on January 24, 2011.2 (vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, supplied for, being supplied for, or may be supplied for, manufactured, or being manufactured for one or more facilities or activities subject to the regulations in this part: Duke Energy had purchased 21 stab assemblies for use in nuclear safety related applications at Catawba and McGuire. Six of these stab assemblies were determined to have been manufactured prior to the vendor drawing change and therefore were not subject to the same defect. Twelve of the defective stab assemblies were stopped in Quality Assurance (QA) Receiving following the failure at Catawba and were never actually available for use in nuclear safety related applications at either site. The remaining three defective stab assemblies had been made available for use in nuclear safety related applications at Catawba. Of these three, one had actually been placed in service (this was the one that failed on June 5, 2010); one had been utilized to replace a missing part in spare equipment and was subsequently tagged for non-use; one had never been installed and was sent to the Duke Energy Metallurgical Laboratory for destructive examination.
No additional defective stab assemblies are in the process of being manufactured for Duke Energy at this time.(vii) The corrective action which has been, is being, or will be taken; the name of the individual or organization responsible for the action; and the length of time that has been or will be taken to complete the action: Following the stab assembly failure described above, the remaining suspect stab assemblies at Catawba and McGuire were placed on hold. (Six stab assemblies received at McGuire were manufactured prior to the vendor drawing change and were not subject to the same defect.) None of the defective stab assemblies were sold or transferred to another nuclear utility. Following the failure of the Catawba stab assembly, additional stab assemblies were tested, a failure investigation was performed, design information was requested from EPSI, and the commercial grade program implications were investigated.
Organizations participating in these corrective actions included site Engineering and Nuclear Supply Chain and the Duke Energy Metallurgical Laboratory.(viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees:
In October 2010, Duke Energy sent an information release concerning the stab assemblies for posting on the Institute for Nuclear Power Operations' Nuclear Network (OE32086).
Following the determination that this issue is 10 CFR 21 reportable, Duke Energy made an initial notification concerning this subject to the NRC Operations Center on January 24, 2011 (Event Number 46568).3