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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML21181A2202021-06-29029 June 2021 Part 21 Written Notification - P21-03302021 Rev. 2 - Failures of Size 1 and 2 Freedom Series Full Voltage Reversing Starters ML21126A1722021-04-29029 April 2021 Paragon Energy Solutions Failures of Size 1 and 2 Freedom Series Full Voltage Reversing Starters ML20108F5302020-03-20020 March 2020 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0129, Rev. 0, Test Stand Deficiency - EMD Fuel Injectors P/N H40084720 ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) GO2-19-129, Part 21 Notification Re Failure Analysis Concluded That Overvoltage Conditions Caused Overheating and the Subsequent Failures of Starter Coils Contained in Spectrum Technologies Buckets2019-09-0303 September 2019 Part 21 Notification Re Failure Analysis Concluded That Overvoltage Conditions Caused Overheating and the Subsequent Failures of Starter Coils Contained in Spectrum Technologies Buckets ML18078A5362018-01-31031 January 2018 Crane Nuclear, Inc. - Interim Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem (Update) ML17311A9092017-10-31031 October 2017 Interim Report for Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem GO2-17-156, Transmittal of 10 CFR 21.21 (d)(4) Notification, GE-Hitachi Relays HMA124A22017-09-0606 September 2017 Transmittal of 10 CFR 21.21 (d)(4) Notification, GE-Hitachi Relays HMA124A2 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 GO2-17-086, 10 CFR Part 21 Notification Regarding Size 1 Freedom Series Starters2017-04-13013 April 2017 10 CFR Part 21 Notification Regarding Size 1 Freedom Series Starters ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17081A4542017-03-17017 March 2017 Part 21 Notification - Evaluation of a Deviation - Starter Contactor Failure ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16251A0982016-09-0202 September 2016 Part 21 - Potential Failure of Battery System Connections ML16188A3762016-06-21021 June 2016 Part 21 Interim Evaluation of Deviation - Contractor Failure ML15211A4962015-07-24024 July 2015 Part 21 - Actuator Shaft Did Not Meet Dimensional Requirements ML14337A0942014-11-24024 November 2014 Notification of Potential Part 21 - Lack of Proper Power Supply Indication ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV 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 ML14169A2582014-06-16016 June 2014 Part 21 - Scram Solenoid Pilot Valve Not Exhausting Properly ML14139A2592014-05-0808 May 2014 10 CFR Part 21 Report Notification, NUS710DU Trip Units ML14134A0792014-05-0808 May 2014 Part 21 - Potential Defect in NUS-710DU Trip Unit to Produce a Valid Trip Output Signal 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 ML14079A0262014-03-11011 March 2014 Notification of Part 21 Re Scram Solenoid Pilot Valve Not Exhausting Properly ML14034A1902014-01-27027 January 2014 Part 21 - Possible Defect in a High Efficiency Particulate Air Filter ML13340A3822013-12-0505 December 2013 Part 21 Reportable Condition Notification: Failure of Relay Logic Card Modules in 2 Out of 4 Voters ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13142A3292013-05-0606 May 2013 Notification of Potential Part 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0109, Rev. 0 ML13127A0142013-05-0303 May 2013 Part 21 Report - Fuel Injectors Failed Pressure Test ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to 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 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 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 ML1035100312010-12-15015 December 2010 Notification of Potential Part 21 Report Concerning Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1035001742010-12-15015 December 2010 Notification of Potential Part 21 Re 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance 2021-06-29
[Table view] Category:Letter type:GO
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023 Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01 GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022 Guarantee of Payment of Deferred Premium GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022 Status of License Renewal Commitments GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-085, Docket No. 50-397, Evacuation Time Estimate Analysis2022-08-30030 August 2022 Docket No. 50-397, Evacuation Time Estimate Analysis GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-22-072, Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing2022-07-11011 July 2022 Summary of Changes and Analysis for Revision 57 of PPM 13.14.4 - Emergency Equipment Maintenance and Testing GO2-22-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process2022-05-25025 May 2022 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Colling Using the Consolidated Line Item Improvement Process GO2-22-062, Registration of Spent Fuel Cask Use2022-05-19019 May 2022 Registration of Spent Fuel Cask Use GO2-22-049, Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors2022-05-10010 May 2022 Supplement to Licensing Amendment Request to Adopt 10CFR50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Rectors GO2-22-054, Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report2022-05-0909 May 2022 Independent Spent Fuel Storage Installation, 2021 Annual Radiological Environmental Operating Report GO2-22-056, Registration of Spent Fuel Cask Use2022-04-21021 April 2022 Registration of Spent Fuel Cask Use GO2-22-055, 2021 Annual Environmental Operating Report2022-04-20020 April 2022 2021 Annual Environmental Operating Report GO2-22-048, 2021 Annual Radioactive Effluent Release Report2022-04-15015 April 2022 2021 Annual Radioactive Effluent Release Report GO2-22-045, Registration of Spent Fuel Cask Use2022-04-0606 April 2022 Registration of Spent Fuel Cask Use GO2-22-044, Level of Financial Protection - Annual Reporting Requirement2022-03-21021 March 2022 Level of Financial Protection - Annual Reporting Requirement GO2-22-038, Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462022-03-0909 March 2022 Docket No. 50-397, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-22-031, Response to Audit Plan and Online Reference Portal Request2022-02-15015 February 2022 Response to Audit Plan and Online Reference Portal Request GO2-22-011, Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report2022-02-0808 February 2022 Docket No. 72-35; Independent Spent Fuel Storage Installation, 2021 Annual Effluent Release Report GO2-22-001, License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-02-0303 February 2022 License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-012, Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report2022-01-24024 January 2022 Independent Spent Fuel Storage Installation - Biennial 50.59/72.48 Report 2024-01-08
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Alex L Javorik ENERGY Columbia Generating Station P.O. Box968, PE04 NORTHWEST Richland, WA 99352-0968 Ph. 509.377.8555 IF. 509.3n.4150 aljavorik@energy-northwest.com April 13, 2017 G02-17-086 10 CFR 21 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 10 CFR 21 NOTIFICATION
Dear Sir or Madam:
Transmitted herewith is 10 CFR Part 21 Notification for Columbia Generating Station.
This report is submitted pursuant to 10 CFR 21.21 (d)(3)(ii). This information was initially reported to the NRC Operations Center on March 16, 2017 (Event Notification #52615).
The attachment to this letter provides the information required by 10 CFR 21.21 (d)(4).
There are no commitments being made to the NRC by this letter. If you have any questions or require additional information, please contact Ms. D.M. Wolfgramm, Regulatory Compliance Supervisor, at (509) 377-4792.
Executed on this /2ftt day of 4/fi / , 2017.
Respectfully, A. L. Jav
- Vice President, Engineering
Attachment:
10 CFR Part 21 Notification cc: NRC Region IV Administrator NRC NRR Project Manager NRC Senior Resident lnspector/988C CD Sonoda- BPA/1399 WA Horin - Winston & Strawn
G02-17-086 Attachment Page 1of3 10 CFR Part 21 Notification AZZ/NLI Supplied Buckets DL0-42-7 AA6D and DL0-42-7 AA48 (i) Name and address of the individual or individuals informing the Commission.
Alex Javorik Vice President of Engineering Columbia Generating Station Energy Northwest PO Box 968 Richland, WA 99352 (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.
Facility:
Columbia Generating Station PO Box 968 Richland, WA 99352 Manufacturer:
AZZ Nuclear I NU 741 O Pebble Drive Fort Worth, TX 76118 Component: Size 1 Freedom Series Starters Part Type: Motor Control Center Cubicle (Bucket)
Defective P/N: 057018COIL-1 /2, 057018COIL-3, 057018COIL-5 (iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
AZZ Nuclear I NU 7410 Pebble Drive Fort Worth, TX 76118 1
G02-17-086 Attachment Page 2 of 3 (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.
Columbia Generating Station's (Columbia) procurement specification required that the Alternating Current (AC) contactor coils be capable of withstanding continuous operation with 528 volts applied to the primary of the Control Power Transformer (CPT). The specification reads: "AC contactor coils shall be capable of withstanding continuous operation with 528 volts applied to the primary of the control power transformer." NLI supplied a starter design that included a secondary coil with a maximum voltage rating of 132 VAC. The CPT, with a primary coil voltage of 528 VAC, supplied voltage in excess of 132 VAC to the secondary coil. Therefore, the supplied coil's limitation of a maximum voltage rating of 132 VAC constitutes a Deviation from the specification.
The excess voltage supplied to the secondary coil results in coil overheating, with the contactors failing to close resulting in an open circuit. Therefore, the contactor is not able to supply power to the load. This is a safety function of the contactor when used to supply power to a safety related load. In accordance with 10 CFR Part 21 reporting of defects, a loss of any safety function of a basic component is a major reduction in the degree of protection and, therefore, a Substantial Safety Hazard. This deviation, were it to remain uncorrected, would constitute a common mode failure to all continuously energized safety related loads that are supplied power from NLI AC buckets during normal or accident conditions, and that contain this type of contactors/starters.
Therefore, the conclusion is that the deviation is a Defect reportable in accordance with 10 CFR Part 21.
(v) The date on which the information of such defect or failure to comply was obtained.
The potential deviation was entered into Columbia's Corrective Action Program (CAP) on January 30, 2017.
The assessment for Part 21 was completed on March 14, 2017, and determined that the reported deviation constituted a defect in accordance with regulatory definitions.
2
G02-17-086 Attachment Page 3 of 3 An officer of the company was notified of the defect and Part 21 reporting requirement on March 14, 2017.
Notification to the NRC of the defect was completed on March 16, 2017 by Event Notification #52615, by the manager of Regulatory Affairs as delegated by the Vice President of Engineering.
(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.
A review of the part numbers found 148 coils installed, 38 coils in stores activities, and 8 coils on order. Eleven of the installed coils were identified as being installed in continuously energized safety related applications.
(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.
Of the eleven motor starter coils identified for replacement, ten have already been replaced with the same make and model of coil. The remaining starter will be replaced by Columbia Generating Station during the next refueling outage (May-June 2017). The continuously operated coils are on a one year replacement plan until a permanent solution can be developed.
(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.
Recommend that licensees fully understand procurement specifications provided to the manufacturer, and verify that the manufacturer met the specification through testing.
(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
Not Applicable 3