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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML22087A0092022-03-0909 March 2022 Ultra Energy, Report Under 10CFR21 of Noncompliance for N7030 Transmitter ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19168A0102019-05-31031 May 2019 Curtis-Wright Nuclear Division- Notification Report for Potential Part 21 Update ML19158A1302019-05-31031 May 2019 Curtiss-Wright Nuclear Division - Notification Report for Potential Part 21 Update ML19078A0872019-03-0808 March 2019 Curtiss-Wright - Interim Notification Report for Potential Part 21 Update ML19053A5002019-02-0101 February 2019 Sor, Inc. Part 21 Notification of Deviation Sor R-Series Housing with Terminal Block ML18289A4572018-10-0808 October 2018 Curtiss-Wright Nuclear Division - Interim Notification Report for Potential Part 21 with Exelon Powerlabs Failure Analysis 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 ML16281A2712016-09-30030 September 2016 Part 21 - Safety Related Component Welding by an Unqualified Welder ML16243A4752016-08-26026 August 2016 Part 21 Safety Related Component Welding by an Unqualified Welder 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 ML15259A5212015-09-10010 September 2015 Part 21 Report - Potential Failure of Electromatic Relief Valve Cutout Switches ML15253A8592015-09-10010 September 2015 GE-Hitachi Nuclear Energy Americas, LLC - Closure of Part 21 60-Day Interim Report Notification: Potential Failure of Electromatic Relief Valve Cutout Switch ML15211A4962015-07-24024 July 2015 Part 21 - Actuator Shaft Did Not Meet Dimensional Requirements ML15169A0082015-06-18018 June 2015 Attachment 1 - Us Plants Potentially Affected ML15169A0092015-06-18018 June 2015 Attachment 2 - 60-Day Interim Report Notification Information Per 21.21(a)(2) ML15169A0102015-06-18018 June 2015 Enclosure 1 - Mfn 15-042 R0 - Description of Evaluation ML15169A0072015-06-17017 June 2015 Part 21 60-Day Interim Report Notification: Potential Failure of Electromatic Relief Valve Cutout Switch ML15161A2302015-06-0404 June 2015 Part 21 Report Regarding Potential Failure of a Time Relay at Quad Cities ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14275A1622014-09-25025 September 2014 Notification of Potential Part 21 Report - Electromatic Relief Valve Excessive Wear 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 ML14197A3802014-07-14014 July 2014 Part-21 Notification-Assembly Errors During Breaker Refurbishment ML14072A3282014-03-13013 March 2014 Part 21 60-Day Interim Report Notification Re Unseating of Valve Spring on SSPV ML14072A3262014-03-13013 March 2014 Enclosure 2: Description of Evaluation ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology 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 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 ML12258A3992012-09-10010 September 2012 Potential Part 21 Issue Related to Tyco Timing Relay ML12219A3042012-08-0202 August 2012 Potential Part 21 Issue Related to Tyco Timing Replay ML12177A0562012-06-21021 June 2012 Part 21 - Reliability Degradation of Resistors in Trip Units and Readout Assemblies ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter with Nonzero Based Calibrations ML12040A2832012-02-0707 February 2012 Notification of Potential Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML12038A0282012-02-0202 February 2012 Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12032A2402012-02-0101 February 2012 Notification of Potential Part 21 - 60-Day Interim Report Notification: Failure of CRD Collet Retainer Tube/Outer Tube Weld ML11228A0842011-08-12012 August 2011 Notification of Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1122401422011-08-11011 August 2011 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1106701742011-02-28028 February 2011 Notification of Potential Part 21 Re Limited E7000 Relay Recall (CII-021) ML1106107042011-02-28028 February 2011 Notification of Potential Part 21 Report - Specified Relays with Degraded Coils ML1104800542011-02-15015 February 2011 Notification of Potential Part 21 Reportable Condition: Crack Indications in Marathon Control Rod Blades 2022-03-09
[Table view] Category:Letter
MONTHYEARIR 05000254/20230042024-02-0505 February 2024 Integrated Inspection Report 05000254/2023004 and 05000265/2023004 ML24004A0052024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0042 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval IR 05000254/20234032023-12-22022 December 2023 Public- Quad Cities Nuclear Power Station Security Baseline Inspection Report 05000254/2023403 and 05000265/2023403 IR 05000254/20230102023-12-20020 December 2023 Comprehensive Engineering Team Inspection Report 05000254/2023010 and 05000265/2023010 ML23349A1622023-12-17017 December 2023 Issuance of Amendment Nos. 298 and 294 Increase Completion Time in Technical Specification 3.8.1.B.4 (Emergency Circumstances) RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 RS-23-123, Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-13013 December 2023 Emergency License Amendment Request - Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23339A1762023-12-0505 December 2023 Notification of NRC Baseline Inspection and Request for Information (05000265/2024001) ML23319A3342023-11-20020 November 2023 Regulatory Audit in Support of License Amendment Requests to Adopt TSTF 505, Revision 2 and 10 CFR 50.69 RS-23-104, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000254/20230032023-11-0909 November 2023 Integrated Inspection Report 05000254/2023003 and 05000265/2023003 RS-23-113, Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 262023-10-20020 October 2023 Submittal of Updated Final Safety Analysis Report (Ufsar), Revision 17 and Fire Protection Report (Fpr), Revision 26 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans ML23206A0382023-09-21021 September 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230112023-09-20020 September 2023 Safety-Conscious Work Environment Issue of Concern Team Inspection Report 05000254/2023011 and 05000265/2023011 RS-23-089, Sixth Ten-Year Interval Inservice Testing Program2023-09-0505 September 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-086, Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-08-28028 August 2023 Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval SVP-23-038, Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities2023-08-14014 August 2023 Owner'S Activity Report Submittal Fifth 10-Year Interval 2023 Refueling Outage Activities IR 05000254/20230022023-08-0808 August 2023 Integrated Inspection Report 05000254/2023002 and 05000265/2023002 ML23178A0742023-08-0707 August 2023 Issuance of Amendment Nos. 296 and 292 Adoption of TSTF-416 Low Pressure Coolant Injection (LPCI) Valve Alignment Verification Note Location ML23216A0362023-08-0707 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI ML23216A0562023-08-0404 August 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 SVP-23-031, Regulatory Commitment Change Summary Report2023-07-14014 July 2023 Regulatory Commitment Change Summary Report ML23181A1062023-06-30030 June 2023 Postponement- Information Meeting (Open House) with a Question-And-Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III ML23179A1932023-06-28028 June 2023 07122023 Letter-Significant Public Meeting to Discuss NRC End-of-Cycle Performance Assessment of Quad Cities Nuclear Plant for Performance for 2022 Calendar Year IR 05000254/20234012023-06-26026 June 2023 Cyber Security Inspection Report 05000254/2023401 and 05000265/2023401 IR 05000265/20230402023-06-22022 June 2023 Reissue Quad Cities Nuclear Power Station 95001 Supplemental Inspection Supplemental Report 05000265/2023040 and Follow Up Assessment Letter RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167B1722023-06-16016 June 2023 95001 Supplemental Inspection Report 05000265/2023040 and Follow-Up Assessment Letter RS-23-060, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2023-06-0808 June 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-23-059, License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-06-0808 June 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23144A3632023-05-26026 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of Quad Cities Nuclear Power Station, Units 1 and 2 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23033A4042023-05-15015 May 2023 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(B) Related to Submission of Subsequent License Renewal Application Letter IR 05000254/20234022023-05-15015 May 2023 Security Baseline and ISFSI Inspection Reports 05000254/2023402, 05000265/2023402, 07200053/2023401 ML23132A2022023-05-12012 May 2023 Annual Radiological Environmental Operating Report ML23125A0612023-05-0808 May 2023 Proposed Alternative to the Requirements of the ASME Code IR 05000254/20230012023-05-0808 May 2023 Integrated Report 05000254/2023001 and 05000265/2023001 RS-22-067, 10 CFR 50.46 Annual Report2023-05-0404 May 2023 10 CFR 50.46 Annual Report ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 RS-23-068, Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell2023-04-28028 April 2023 Response to Request for Additional Information for Quad Cities Relief Request I6R-11, Proposed Alternatives for a Temper Bead Weld Repair of the Mating Surfaces of the Reactor Pressure Vessel Head and Shell SVP-23-018, Radioactive Effluent Release Report for 20222023-04-28028 April 2023 Radioactive Effluent Release Report for 2022 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23110A0622023-04-25025 April 2023 Transmittal of Final Quad Cities Nuclear Power Plant, Unit 1 Accident Sequence Precursor Report (Licensee Event Report 254-2022-001) ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration 2024-02-05
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Scott Daubert Quality Assurance Manager Tyco Electronics Global Aerospace Tyco Electronics Defense and Marine Division CII Relays Asheville Operations 1396 Charlotte Highway Fairview, NC 28730 Date: February 28, 2011 Telephone: 828-338-1011 Operation Center Fax: 828-338-1103 To:
United States Nuclear Regulatory Commission (NRC)
Fax: (301) 816 - 5151
Subject:
Notification of Limited E7000 Relay Recall (CII-021)
During our dedication process of nuclear E7000 relays, Tyco Electronics experienced an issue with a component. The coil, internal to the relay, failed to operate during quality assurance testing.
We purged this lot of coils from our inventory and all "work in process". We are able to account for all the coils in this lot. Our records indicate that some relays shipped to your facility were made using this specific coil lot.
Because the coil did not meet stated requirements, we are recalling the specific relays listed on the attached certificates of conformance for replacement. Note that only the specific lot numbers listed on the attached certificates of conformance are affected by this recall. All other lots should function in accordance with specifications.
To return these 'relays, contact your Tyco Electronics Customer Service Representative at 1-800-526-5136 to obtain a Customer Return Authorization number (RMA#) and then follow the standard return process. Please reference "CII-021" on RMA paper work. Relays should be returned to my attention.
Ifyou have any questions or require any additional information on this limited recall, please contact me at the numbers listed above.
Sincerely, Scott Daizbert Quality Assurance Manager Part 21 Notification 1 of 3 CII-021
- Tyco Electronics Attachment I Customers notified by Tyco Electronics regarding this condition.
Tyco/Canada Markham, Ontario, Canada 5 Exelon/Quad Cities Cordova, IL 2 Total 7 Part 21 Notification 2 of 3 CII-021
Tyco Electronics Attachment 2 Transfer of Information per Part 21.21 (b)
(i) Name and address of the individual providing the information:
Rob Hughes, Quality Engineer, Tyco Electronics - CII of the Global Aerospace and Defense Division, 1396 Charlotte Highway, Fairview, NC USA 28730.
(ii) Identification of the facility, the activity, or the basic component supplied for such facility or such activity that contains a deviation or failure to comply; Item supplied are E7000 relays with serial numbers beginning with 1046, and that have this specific lot of coils. The Certificates of Conformance stating exact relay description and serial numbers were sent to affected customers with this February 28, 2011 notification.
Tyco sold this safety-related item for specified and unspecified applications. The customers for which Tyco had insufficient information to complete the Part 21 evaluation are listed in Attachment 1.
(iii) Identification of the firm constructing the facility or supplying the basic component that contains a deviation or a failure to comply:
Tyco Electronics, 1396 Charlotte Highway, Fairview NC, USA 28730 (iv) Nature of the defect or safety hazard that could be created by such a deviation or failure to comply:
A coil failed to operate during the dedication testing of a current production order. We are recalling relays of this same material lot that were previously shipped. It is possible that the relays with this lot of coils may fail to operate at some point in this products' life cycle, thereby preventing the relay from changing state when activated.
(v) The date on which the information of such a deviation or failure to comply was obtained Tyco Electronics made the determination of the existence of this condition February 25, 2011. Notice of Limited E7000 Relay Recall was issued to the customers on February 28, 2011.
(vi) In case of a basic component, which contains a deviation or failure to comply, the locations of all such components in use or being supplied?
Customers that purchased affected safety-related items from Tyco Electronics for unspecified applications are identified in Attachment 1.
(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 (note, these are actions specifically associated with the identified deviation or failure to comply:
Tyco purged the specific lot of coils failing to meet specification from its inventory and "work in process".
(vii) Any advice related to the deviation or failure to comply about the facility, activity, or basic component that has been, is being given to purchasers or licensees:
Based on our evaluation this issue is expected to have a high potential to produce a significant safety concern. However, Tyco Electronics does not have sufficient information to perform an evaluation for unspecified applications. Therefore customers having received the recall notification should return affected relays for a replacement.
Part 21 Notification 3 of 3 CII-021