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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23241A0022023-08-25025 August 2023 Paragon Final Part 21 Report on Defect with Eaton/Cutler Hammer Size 4 and 5 Freedom Series Contactors Modified by Paragon with Special Coils And/Or with RTV to Improve the Securing of Shading Coils ML23221A3702023-08-0303 August 2023 Paragon Energy Solutions, 10CFR Part 21 Initial Notification: P21-08032023-IN, Rev. 0 ML21181A2202021-06-29029 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 ML20366A0472020-11-18018 November 2020 Curtiss-Wright 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid Batch 17BLVS293 ML20255A2002020-07-21021 July 2020 Paragon Energy Solutions, Failures of Size 1 and 2 Freedom Series Auxiliary Contacts ML19253A0532019-08-29029 August 2019 Azz Nuclear - Report of Potential 1O CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19168A0122019-05-31031 May 2019 Paragon Energy Solution LLC-10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML19120A1062019-04-17017 April 2019 Interim Report of Potential 10 CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML19121A1552019-04-15015 April 2019 Curtiss-Wright Nuclear Division, Enertech - 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML17090A3982017-03-27027 March 2017 Engine Systems, Inc. - Part 21 Report Regarding Identification of Failed Diode Surge Suppressor with Internal Manufacturing Defect ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling 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 ML16188A3762016-06-21021 June 2016 Part 21 Interim Evaluation of Deviation - Contractor Failure ML16154A2052016-05-20020 May 2016 Part 21 Interim Evaluation of a Deviation - Contactor Failure ML15303A0072015-10-26026 October 2015 Part 21 Report Regarding Speed Switch Capacitor Failure, Per Shearon Harris Plant ML15314A0312015-10-23023 October 2015 Engine Systems, Inc. - 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0113, Rev. 0, Per Shearon Harris Nuclear Plant ML15099A0422015-04-0202 April 2015 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML15099A0432015-04-0202 April 2015 Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches ML14274A0522014-09-22022 September 2014 Final Report 10CFR Part 21 Evaluation Regarding Misaligned Separators in LCR-25 Standby Batteries, Revision 1 - Original Letter Did Not Include the List of Affected Utilities ML14213A0992014-07-24024 July 2014 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML14169A0302014-06-15015 June 2014 Update to Interim Report - 10CFR 21 Evaluation Regarding Potential Deficiencies in Seismic Qualifications for PV-62 ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13099A2382013-03-27027 March 2013 Notification of Potential Part 21 Report Re Series 24 Csr Relays with Oversized Cam Drive Components 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 ML12123A0892012-04-27027 April 2012 Abb, Inc., Notification of Potential Part 21 Report - Hk Circuit Breaker Studs Failed to Meet Specification ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12075A1062012-03-14014 March 2012 Notification of Potential Part 21 Re Defect on Arvan Electrical Terminal Blocks ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter with Nonzero Based Calibrations ML11186A8912011-07-0101 July 2011 Notification of Potential Part 21 Seal Failure and Leakage Associated with Model B5497-301 Valves ML0926802462009-09-23023 September 2009 Notification of Potential Part 21 on Reportable Occurrence Under 10 CFR Part 21: Firmware Anomaly in the Model RM-80 Radiation Monitoring System ML0831900172008-11-12012 November 2008 Notification of Potential Part 21 on All Dimensionally Verified Commercial Grade Items Processed Per Fisher Manufacture Procedure Fmp 2K28 ML0823901062008-08-25025 August 2008 Notification of Potential Part 21 on Failure of F and G Switches ML0809906342008-04-0404 April 2008 Part 21 Notification Regarding Failure to Comply with the Requirements for Dedication of Commercial Grade Items ML0734402112007-12-0707 December 2007 Deficiency Report Part 21 Potential Insufficient Thread Engagement for Certain Pressure Transmitters ML0732000862007-11-0909 November 2007 Notification of Potential Part 21 Report Conval Valves Weld Qualifications ML0713703092007-03-0707 March 2007 Velan, Inc., Piston Check Cv Information ML0618603812006-06-30030 June 2006 Operations Center Event Report, Defective Paperless Data Acquisition Recorders. ML0609504012006-04-0303 April 2006 Director Office of Inspection & Enforcement Reference: 10 CFR 21 Notification of 3/30/06 Rev1 2023-08-03
[Table view] Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 ML22138A4012022-05-26026 May 2022 Project Manager Reassignment ML22101A2822022-05-0606 May 2022 Regulatory Audit Summary Related to the Review of License Amendment Regarding Revising the Flood Hazard Protection Scheme IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 ML22034A5352022-02-0202 February 2022 Notification of Licensed Operator Initial Examination 05000400/2022301 2024-01-30
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Date: 7/21/2020 To: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Fax Number (301)816-5151 10CFR Part 21 Formal Notification: P21-06032020, Rev. 1
Subject:
Failures of Size 1 and 2 Freedom Series Auxiliary Contacts Pursuant to 10CFR 21.21 (d)(3)(ii), Paragon Energy Solutions is providing formal notification of the identification of a defect.
The following information is required per 10CFR 21.21 (d) (4).
(i) Name and address of the individual or individuals informing the Commission.
Tracy Bolt, Chief Nuclear Officer Paragon Energy Solutions 7410 Pebble Drive Ft. Worth, TX 76118 (ii) Identification of the facility, activity, or the basic component supplied for such facility or such activity within the United States which fails to comply or contains a defect.
DUKE Harris Nuclear Plant (iii) Identification of the firm constructing or supplying the basic component which fails to comply or contains a defect.
Paragon / NLI 7410 Pebble Dr. Fort Worth, Texas 76118 Paragon Energy Solutions 7410 Pebble Drive
- Fax 817-590-0484 Page 1 of 6
(iv) Nature of defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply.
DUKE Harris Nuclear Plant (HNP) has identified instances where Size 1 and 2 Eaton Freedom Series starters have failed to function as expected in assemblies that were originally supplied by NLI. The auxiliary contacts have degraded prematurely and have failed to change state when the starter was energized which has affected indication and other controlling actions within the circuit.
The premature degradation of the auxiliary contacts with the old model NLI special coil, p/n:
057018-COIL-1/2 coupled with the old model control power transformer (CPT), has occurred on size 1 & 2 contactors that were continuously energized with significant run time after approximately 3-5 years of service time. HNP has provided information that to manage the known degradation, the auxiliary contacts should be replaced at an increased frequency until new auxiliary contacts are installed along with the new design NLI special coil, p/n: 057018-COIL-1/2-M.
Based on information provided by HNP; if HNP personnel had not identified the degraded auxiliary contacts (failure mechanism and new expected service time), this deviation could have resulted in a loss of safety function since these auxiliary contacts and old style coils are installed on numerous safety-related air handlers and pumps. Depending on whether the left-side aux contact block or right-side contact block is degraded, determines the impact on safety function of a specific component. Both the left and right-side aux contact blocks are susceptible to premature degradation. Note that some of the impacted air handlers have redundant air handlers in the respective equipment areas that may provide cooling to maintain the safety function. However, there are numerous components that support a safety function on a single train which may be lost if an aux contact failure were to occur.
The identified starters have been installed for 3-5 years, operating in a continuous duty application.
(v) The date on which the information of such defect or failure to comply was obtained.
June 1, 2020 Part 21 Report No: P21-06032020, Rev. 1 Page 2 of 6
(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.
Location of the units installed:
DUKE Harris DUKE Oconee NextEra Turkey Point Energy Northwest Columbia Dominion North Anna The part numbers of the affected starters are as follows Eaton Part numbers Comments Eaton Part number designators AN16DN0AB AN16 = Non Reversing Starter When the NLI special coil was AN16DN0AB-T16 CN15 = Non Reversing Contactor first introduced the part number AN16GN0AB CN55 = Reversing Contactor of the starter was not changed.
AN16GN0AB-T16 The description of the item T16 = with ring tongue terminals CN15DN3AB included a statement such as:
CN15DN3AB-T16 "With NLI Special Coil Part DN = Size 1 CN15GN3AB Number 057018-COIL-1/2" GN = Size 2 CN55DN3AB For process improvement, NLI utilized an NLI part number to distinguish the NLI CN55GN3AB version with the special coil from the stock version from Eaton. The part number CN55GNY1A varied by project.
NLI Part Number designations Suffix NLI-AN16DN0AB-MOD "MOD" = Contains the Original NLI Coil P/N: 057018-COIL-1/2 AN16GN0AB-T16 SPECIAL "Special" = Original NLI Coil P/N: 057018-COIL-1/2 AN700DN022A-T16 SPECIAL CN55GN3AB-T16-SPECIAL "M" = New NLI Coil P/N: 057018-COIL-1/2-M (Not affected by this Notification)
NLI Coil Part number 057018-COIL-1/2 = Original Coil for Size 1 and Size 2 057018-COIL-1/2-M = New Coil for Size 1 and Size 2 Part 21 Report No: P21-06032020, Rev. 1 Page 3 of 6
The number of units at each facility is not known as the issue is only related to the units in a continuous duty application.
The nature of the defect is the pre-mature aging of the component within the auxiliary contact mechanism that is adjacent to the operating coil. The starter coil is potentially being subjected to voltages of a nature that elevates the temperature within the starter adjacent to the auxiliary contacts.
The specific units at HNP that have experienced the damage have been identified and the run times vary from 5 years cycling on and off on 2 week intervals, to 3 years operating in a continuous running application.
Continuous duty application is based on a run time that allows for the unit to reach thermal equilibrium.
(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.
The root cause of the degraded component is due to the increased voltage and the overall temperature of the starter coil at the elevated voltage. This elevated voltage and temperature has degraded the mechanism of the auxiliary contact operator to a point to which it has become separated from the parent component. See example figures below.
Part 21 Report No: P21-06032020, Rev. 1 Page 4 of 6
Paragon/NLI has investigated the root cause of this issue. The root cause of this issue (elevated voltage) is the same as previous notifications that have been reported. Paragon/NLI has developed the proposed solution below in (viii). In addition, Paragon/NLI has developed a new version of the special coil, (P/N: 057018-COIL-1/2-M) that operates at a lower temperature than the original special coil that is currently in use at HNP. When the new version of the special coil is subjected to the same voltages, the temperature is lower.
(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.
The current configuration of the size 1 and size 2 motor control center cubicles at HNP that were supplied by NLI, includes a control transformer that has a nominal 4:1 turns ratio (the CPT has an actual turns ratio of ~3.7:1). What this actual turns ration does is boosts the secondary voltage of the CPT. Effectively, with no load at 480VAC input, the output on the control circuit will be approximately 129VAC instead of 120VAC. However, at 508 VAC input (HNP nominal bus voltage), the no load voltage would be approximately 137 VAC. This exceeds the rated control circuit voltage of 132VAC. During normal operation it is expected that there is a load on the control circuit since the control transformer is providing power to the starter, relays lights and other components that are connected to the control circuit of the MCC cubicle. This load varies with each cubicle based on the specific application and the number of accessories that are being energized. This loading will cause the control voltage at the coil terminals to droop, however it has been noted in some instances that, even with this Part 21 Report No: P21-06032020, Rev. 1 Page 5 of 6
droop, the rated control voltage of 132VAC is still being exceeded. This additional voltage applied along with the original special coil generates the additional heat that is causing the premature degradation/aging of the auxiliary contact component.
It is recommended that the starters and coils be replaced in the applications where the units are being operated in a continuous duty application. It is also recommended that the control transformer be replaced with a true 4:1 ratio transformer. Paragon/NLI has developed a true 4:1 ratio transformer that will provide additional mitigation of this potential over-voltage condition. Replacing the transformer with a true 4:1 ratio, reduces the control voltage that is being applied to the control circuit in a manner that will not prevent the unit from providing a sufficient voltage during a degraded voltage condition, and also will not subject the components to a voltage above the ratings when the supply voltage is operated above the nominal 480 VAC bus voltage.
Paragon has no other recommendations, as the accelerated aging of the components and the expected life based on the additional heat the units have been subjected to is unknown.
Tracy Bolt Chief Nuclear Officer Paragon Energy Solutions 817-284-0077 tbolt@paragones.com Part 21 Report No: P21-06032020, Rev. 1 Page 6 of 6