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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML19158A1302019-05-31031 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 ML18332A1222018-11-15015 November 2018 Curtiss-Wright - Interim Notification Report for Potential Part 21 Update ML15259A5212015-09-10010 September 2015 Part 21 Report - Potential Failure of Electromatic Relief Valve Cutout Switches ML15161A2302015-06-0404 June 2015 Part 21 Report Regarding Potential Failure of a Time Relay at Quad Cities 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 ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve 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 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 ML12226A0022012-08-0202 August 2012 Revision to Notification Date 07/31/2012 Regarding Manufacturing Defect in a Timing Relay Which Prevents the Relay from Operating at a Specific Setting ML12219A3042012-08-0202 August 2012 Potential Part 21 Issue Related to Tyco Timing Replay 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 ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0623700952006-08-21021 August 2006 Update to Part 21 Interim Report Notification: Failure Analysis of Core Shroud Repair Tie Rod Upper Support Crack ML0232901622002-11-18018 November 2002 Final Report, Stability Option III: Possible Successive Confirmation Count Resets - Not Reportable 2019-05-31
[Table view] 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:E-Mail
MONTHYEARML24254A2082024-09-10010 September 2024 NRR E-mail Capture - Quad Cities, Unit Nos. 1 and 2 - Alternative to RV-08, Rev 1, SRV Testing Interval - Acceptance of Requested Licensing Action Re Relief Request Associated with Safety Relief Valve Testing Interval ML24250A1062024-09-0606 September 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24197A0482024-07-12012 July 2024 Information Request for the Quad Cities Nuclear Station Biennial Problem Identification and Resolution Inspection ML24135A0182024-05-13013 May 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 Amendment ML24131A0612024-05-10010 May 2024 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Proposed Alternative to Utilize Code Case OMN-32 (L-2024-LLR-0030) ML24086A5182024-04-30030 April 2024 E-mail to Christian Williams Decision on the Exemption Request for Quad Cities ML24086A4782024-04-24024 April 2024 Email to Christian Williams Availability of Environmental Assessment for the Quad Cities Exemption ML24114A1702024-04-15015 April 2024 Request for State Review of the Quad Cities HI-STORM Exemption Request Environmental Assessment ML24102A2422024-04-10010 April 2024 NRR E-mail Capture - Draft Request for Additional Information Quad Cities TSTF-505 and 50.69 Amendments ML24089A0102024-03-29029 March 2024 NRR E-mail Capture - Quad Cities Unit Nos. 1 and 2 - Alternative to Core Spray Pump Testing - Acceptance of Requested Licensing Action Relief Request Associated with the Sixth Inservice Testing Interval ML24066A1532024-03-0606 March 2024 NRR E-mail Capture - Request for Additional Information TSTF-505, R2, Provide Risk-Informed Extended Completion Times, RITSTF (Risk-Informed Technical Specification Task Force) Initiative 4b and 10 CFR 50.69 License Amendments ML23349A0362023-12-14014 December 2023 NRR E-mail Capture - Draft Request for Additional Information Re Quad Cities Emergency Amendment Related to Unit 1 Diesel Generator Inoperability ML23338A1192023-11-21021 November 2023 NRR E-mail Capture - Draft Request for Additional Information Quad Cities Relief Request I5R-26 ML23268A0022023-09-22022 September 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-264-A, Revision 0 ML23264A7992023-09-21021 September 2023 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1 ML23262A7432023-09-19019 September 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 Acceptance of Relief Request I5R-26 ML23186A1412023-07-0505 July 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-505 ML23186A1482023-07-0505 July 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt 10 CFR 50.69 ML23163A2292023-06-12012 June 2023 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-580, Revision 1 ML23118A1652023-04-28028 April 2023 NRR E-mail Capture - Request for Additional Information Quad Cities, Unit 2, Alternative Request I6R-11 ML23083B9572023-03-24024 March 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-564 ML23055A0392023-02-24024 February 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Amendment to Adopt TSTF-416 ML23052A0772023-02-21021 February 2023 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance Timely Renewal Exemption Request ML22357A0392022-12-23023 December 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of I6R-10 Related to Repair of Penetration N-11B ML22354A2622022-12-20020 December 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of Request to Use Certain Provisions of the 2019 Edition of the ASME BPV Code, Section XI ML23004A0262022-12-16016 December 2022 NRR E-mail Capture - Draft Request for Additional Information - Quad Cities Alternative RV-04, Inservice Testing of High Pressure Coolant Injection Drain Pot Solenoid Valves (EPD L-2022-LLR-0070) ML22348A0452022-12-14014 December 2022 NRR E-mail Capture - Draft Request for Additional Information Regarding Quad Cities Alternative I6R-09 ML22301A0902022-10-28028 October 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request - Acceptance of License Amendment Request to Adopt TSTF-301, Revision 2 ML22290A0662022-10-17017 October 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-04 Related to HPCI Drain Pot Solenoid Valve Testing ML23079A0272022-10-0505 October 2022 Licensee Outline Submittal Email (Quad Cities, 2023) ML22256A0112022-09-12012 September 2022 NRR E-mail Capture - Request for Additional Information LaSalle County Station, Units 1 and 2 and Quad Cities Nuclear Power Station, Units 1 and 2 License Amendments Related to Fuel Storage ML22224A0222022-08-12012 August 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative I6R-09 Related to Use of Certain 2013 Edition ASME Code Requirements ML22200A0782022-07-19019 July 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Fleet Request to Use Honeywell Mururoa V4F1 R Supplied Air Suits ML22206A0352022-07-13013 July 2022 NRR E-mail Capture - Draft RAI Quad Cities Alternative Related to Sblc Nozzle Inspection ML22193A0412022-07-11011 July 2022 NRR E-mail Capture - RAI Quad Cities License Amendment to Expand the Use of Prime Methods ML22187A1832022-07-0606 July 2022 NRR E-mail Capture - Completion of Activities Related to EPID L-2022-LLD-003, Quad Cities Potential NOED ML22182A1992022-07-0101 July 2022 NRR E-mail Capture - RAI Alternative RV-11, Code Case OMN-28 ML22164A8582022-06-13013 June 2022 NRR E-mail Capture - RAI Alternative RV-09, MSSVs ML22164A8562022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Alternative RV-08, Safety Relief Valves ML22164A7852022-06-13013 June 2022 NRR E-mail Capture - RAI Quad Cities Amendment for Spent Fuel Pool Storage Analysis ML22101A0932022-04-11011 April 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Relief I6R-01 Related to SLC Nozzle Inner Radius Inspection ML22077A4122022-03-18018 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-06 Related to MSSV Setpoint Testing ML22076A0322022-03-17017 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-03 Related to PIV Leak Test Frequency ML22075A0752022-03-16016 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-07 Related to MSIV Stroke Testing ML22068A1512022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-10 Related to Code Case OMN-28, MOV Testing ML22068A0552022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-09 Related to MSSV Testing ML22068A0062022-03-0909 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative RV-11 Related to OMN-28, Valve Position Verification ML22067A2172022-03-0808 March 2022 NRR E-mail Capture - Quad Cities Nuclear Power Station, Units 1 and 2 - Acceptance of Alternative Related to MSRV Testing ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 2024-09-06
[Table view] Category:Letter
MONTHYEARIR 05000254/20244022024-09-12012 September 2024 Material Control and Accounting Program Inspection Report 05000254/2024402 and 05000265/2024402 (Public) SVP-24-054, Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds2024-09-11011 September 2024 Deviation from BWR Vessel and Internals Project (BWRVIP) Guidelines - Inspection of Top Guide Rim Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000254/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Quad Cities Nuclear Power Station (Report 05000254/2024005; 05000265/2024005) RS-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval ML24183A1082024-08-0808 August 2024 – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b SVP-24-049, Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities2024-08-0707 August 2024 Owners Activity Report Submittal Sixth 10-Year Interval 2024 Refueling Outage Activities IR 05000254/20243012024-08-0101 August 2024 NRC Initial License Examination Report 05000254/2024301; 05000265/2024301 SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel SVP-24-046, Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure2024-07-22022 July 2024 Turbine Trip and Automatic Scram Due to Digital EHC Power Supply Intermittent Failure RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions SVP-24-041, Regulatory Commitment Change Summary Report2024-07-0505 July 2024 Regulatory Commitment Change Summary Report SVP-24-043, Registration of Use of Casks to Store Spent Fuel2024-07-0505 July 2024 Registration of Use of Casks to Store Spent Fuel ML24162A0982024-07-0303 July 2024 – Issuance of Amendment Nos. 301 and 297 Adoption of 10 CFR 50.69 Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations SVP-24-039, Ile Post Exam Package Letter2024-06-12012 June 2024 Ile Post Exam Package Letter RS-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed ML24110A0492024-05-28028 May 2024 Audit Report Related to the TSTF-505 and 10 CFR 50.59 Amendments ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24141A2102024-05-20020 May 2024 Operator Licensing Examination Approval - Quad Cities Nuclear Power Station, May 2024 RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report IR 05000254/20240012024-05-14014 May 2024 Integrated Inspection Report Nos. 05000254/2024001 and 05000265/2024001 SVP-24-034, Annual Radiological Environmental Operating Report2024-05-10010 May 2024 Annual Radiological Environmental Operating Report SVP-24-031, Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing2024-05-10010 May 2024 Automatic Actuation of Reactor Protection System During Scram Discharge Volume Leak Rate Testing RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report ML24109A0662024-05-0202 May 2024 – Relief Request I5R-26, Revision 0 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests SVP-24-029, Radioactive Effluent Release Report for 20232024-04-26026 April 2024 Radioactive Effluent Release Report for 2023 SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24114A1712024-04-23023 April 2024 State of Illinois (IEMA-OHS) Comment Quad Cities HI-STORM Exemption Environmental Assessment RS-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion SVP-24-024, Corrected Radioactive Effluent Release Report for 20222024-04-0505 April 2024 Corrected Radioactive Effluent Release Report for 2022 IR 05000254/20245012024-04-0505 April 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000254/2024501 and 05000265/2024501 RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report SVP-24-023, Ile Outline Submittal Letter2024-03-29029 March 2024 Ile Outline Submittal Letter RS-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS ML23340A1552024-03-15015 March 2024 – Issuance of Amendment Nos. 299 and 295 Adoption of TSTF-564, Safety Limit MCPR SVP-24-018, Ile Proposed Exam Submittal Letter2024-03-13013 March 2024 Ile Proposed Exam Submittal Letter RS-24-015, Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval2024-02-29029 February 2024 Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval IR 05000254/20230062024-02-28028 February 2024 Annual Assessment Letter for Quad Cities Nuclear Power Station, Units 1 and 2 (Report 05000254/2023006 and 05000265/2023006) ML24053A1192024-02-22022 February 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000265/2024010 and 05000254/2024010 IR 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 2024-09-04
[Table view] |
Text
From: Hover. Margie To: Hoc HOO X Cc: Hover. Margie
Subject:
[Extemal_Sender] Curtiss-Wright Transmittal DT193199 (PO# N/A): Response required [#DDDTIHUIHYQE#]
Date: Friday, May 31, 2019 11:06:22 AM Attachments: Notification Report for Potential Part 21 Update Event ML18289A457 Log No. 2018-24-00.pdf Document Control Workflow Notification
Dear Customer,
Please confirm receipt of attached documentation by replying Yes to this email.
Responding Yes not only confirms your receipt, but also initiates an update of our Submittal/Tracking Transmittal Database.
Thank you.
NOTICE: The documents listed in the DT below will be delivered via attachments to this email.
[ J __ J DOCUMENT Contract TRANSMITTAL N/A
Nuclear Division 4600 East Tech Number Customer/Vendor Drive, Cincinnati, OH DT193199 Purchase Order Number 45245 N/A T: 513.528.7900 I F:
513.528.4537 Originated By Originated Date Project Hover, Margie 5/30/2019 lOCFR PART 21 REPORT UPDATE Name Company Email Headquarters Operation U.S. Nuclear Regulatory hoo.hoc@nrc.gov Officer Commission Document Number Rev Document Type Qty For ...
lOCFR Part 21 Report N/A Report 1 Final Record
Remarks ACKNOWLEDGMENT:
Please confirm receipt of the referenced documentation by replying Contact Information for Originator of Part-21 "YES" to the email you Notification: received. The referenced documentation will default TIM FRANCHUK to a status of Curtiss-Wright Nuclear Division UNCONTROLLED if your Director of Quality "YES" reply is not received (513) 201-2176, within 30 days.
tfranchuk@curtisswright.com Notification Report for Potential Part 21 Update:
Namco Limit Switch PIN: EA 700-90964 U.S. Nuclear Regulatory Commission ATTN: NRC Document Control Desk Washington, DC 20555-0001 Phone: (301) 816-5100 Fax: (301) 816-5151 Document Control Use Only Transmitted By Transmitted Date Hover, Margie 5/31/2019 020-07-91 Rev. 6 For simplicity, EasyResponse is enabled; You can simply reply with a valid outcome such. as yes or no on a line by
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- CURl1SS- Nuclear Division 4600 East Tech Drive WRIGHT Cincinnati, OH 45245 T: 513.528.7900 IF: 513.528.9292 www.curtisswright.com/NuclearDivision May 31, 2019 U.S.. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
Notification Report for Potential Part 21 update.
Dear Sir or Madam:
In reference to the Curtiss-Wright Interim Notification Report dated 10/8/2018 (Event No. ML18289A457/Log No. 2018-24-00) for an EA700-90964 limit switch failure, the following updates are provided.
Curtiss-Wright was notified on August 7th, 2018 by Exelon's Quad Cities Plan~,that a Curtiss-Wright Supplied*Namco Limit Switch, PIN: EA 700-90964 had failed during a planned maintenance test. ,
The switch was found to be sluggish in returning to the normal shelf state after actuation, or would not return at all. The switch was identified as Curtiss-Wright Tag# ST34603 and was provided as a safety related component to Exelon in September 2005. According to Exelon, the item was stored for 8 years then failure occurred roughly four and a half years into service. The part has a manufacturer date coded as August 2005.
The switch was subsequently sent to Exelon Powerlabs where a detailed failure evaluation was performed (See QDC-07067). Exelon Powerlabs confirmed the failure mode and determined that there was insufficient lubrication in place to support normal switch function. The switch was then sent to Namco for further evaluation and Namco confirmed the lack of lubrication.
Note that in subsequent discussions after release of the QDC-07067 report, Namco indicated that their statement on the lack of lubrication was an observation of the switch's current condition, and not the cause of the failure.
References (attached):
Exelon Powerlabs Initial Report QDC-07067 08/08/2018 on failed Switch Exelon Powerlabs 2nd Report QDC-62770 Rl 05/09/2019 on used Switches Namco Report Mechanical Cycle Testing, EA700-90964 Commercial Limit Switch (Final Report- 28May2019)
Initial Report QDC-07067
Conclusions:
Initial Failure occurred roughly four and a half years in service where switch* "binding was due to insufficient (i.e. dried out) lubrication on the moving parts". The shaft 0-ring was sevijrely hardened.from aging, "which could have contributed to binding".
Second Report QDC-62770:
Per Table 1, pg. 3: SN 05, 09, & 02 were installed for 6 years without a failure.
Pages 16 & 17 photos show these 3 switches are without lubrication and had wear patterns between tile slide & the outer housing, similar to the failed switch.
Per pg. 1: CQ1400801 S/N 03 was installed for approximately 9 months.
Page 17 photo shows significant lubrication and the same wear pattern.
The foreign material found in the switches were identified as paint residue (due to wear).
Page 1 of 2
- CURTISS- Nuclear Division 4600 East Tech Drive WRIGHT Cincinnati, OH 45245 T: 513.528.7900 IF: 513.528.9292 www.curtisswright.com1Nuclear0ivision Shaft 0-Rings on the 6 years in service switches were severely hardened and embrlttled due to aging, while the 9 month switch's 0-Ring was still in good condition, but beginning to show signs of aging as noted by an increase in hardness.
NAMCO Cycle Aging Report:
Report showed the results of Mechanical Cycle Testing on two new switches, which was performed in the same orientation as the Exelon application. The purpose of this test was to prove that with/without lubrication, at the known rate of cydes, these units would not have experienced the amount of wear indications noted in Exelon Powerlabs' reports r~gardless of the amount of lubrication present. One switch was completely lubricated and one was without any lubrication. These were cycled for 4800 cycles and were both functional at the end of testing.
Curtiss-Wright noted that Namco's testing was done at laboratory ambient conditions, and did not account for other external factors such as typical system vibrations and operating temperature present in Quad Cities application.
CW
Conclusion:
Based upon similar wear patterns, the presence of "significant grease" does not resolve wear pattern issue caused in a shorter period of time, thus the lack of grease can be considered to "not be a significant credible failure mechanism" (same or no grease between shuttle and housing). Based upon the NAMCO report, the presence or lack of grease has no impact on wear or operability and thus does not affect the safety function.
, In addition, the CQ1400801 S/Nj)3 installed for9 months, the 0-Ring measured an 81 durometer hardness (showing aging) but not brittle. The other 3 installed for 6 years were brittle but did not affect operability. Thus the hardness of the 0-Rings can be considered to "not be a significant credible failure mechanism".
All four switches in Report QDC-62770 had paint scrapings caused by wear which was present and operated properly after being in service for an extended period of time. Thus the presence of paint residue due to wear can be considered to "not be a significant credible failure mechanism".
There have been no other reported failures of this type. The root cause failure mechanism has not been identified, thus this switch faihire does not aP. ear to represent a common mode failure.
m Tim Franchuk Director, Quality Assurance Curtiss-Wright Nuclear Division, Cincinnati Operations 513-201-2176 TFranchuk@CurtissWright.com Page 2 of Z