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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification WO 23-0002, Written Part 21 Notification of a Defect Associated with Imi CCI Supplied Main Steam and Main Feedwater Isolation Valves2023-01-11011 January 2023 Written Part 21 Notification of a Defect Associated with Imi CCI Supplied Main Steam and Main Feedwater Isolation Valves ML22220A2362022-08-0202 August 2022 Leonardo DRS, 16-AAT907B Power Supply 10 CFR Part 21 Notification ML19346H8732019-12-12012 December 2019 Westinghouse Electric Company - Notification of the Potential Existence of Defect Pursuant to 10 CFR Part 21 ML19168A0122019-05-31031 May 2019 Paragon Energy Solution LLC-10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML18039A2922018-01-24024 January 2018 Velan, Inc. - Corrected Notification for 4NPS Class 150 Through 900 Swing Check Valve Disc (Part Number 8205-012) ML18024A0032018-01-16016 January 2018 Velan Inc. - Part 21 Notification for Disc (Part Number 8205-012) in 4NPS Class 150 Through 900 Swing Check Valve 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 ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards ML17104A2882017-04-13013 April 2017 Emerson Process Management, LLC - Fisher Information Notice, (FIN) 2017-02 ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16278A4712016-09-22022 September 2016 Notification of 10 CFR Part 21 Condition, Masterpact Breaker Fail to Close ML16281A2702016-09-22022 September 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16229A4442016-08-15015 August 2016 Potential Part 21 on Safety Clip, Siemens Part Number 401158 ML16203A1792016-07-0707 July 2016 Curtiss-Wright 10 CFR Part 21 Report Regarding Disposition of a Nonconformance on Struthers-Dunn Relay Part Number B225XCXP125V Supplied to PSEG Nuclear, LLC ML16139A8342016-05-10010 May 2016 Electroswitch - Transmittal of 10CFR Part 21 Reporting of Defects and Noncompliance Regarding Vendor Inspection of Electroswitch Corporation Docket No. 99900833 ML16126A1112016-04-29029 April 2016 National Technical Systems (Nts) Request for Extension, for Potential Part 21 on Safety Clip, Siemens Part Number 401-158 ML16112A2102016-03-14014 March 2016 National Technical Systems - Potential Part 21 on Siemens 401-158 Safety Clip, Per Wolf Creek, Salem, and Arkansas Nuclear One ML15103A4852015-04-0707 April 2015 Itt Engineered Valves - 2nd Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M I Diaphragms, Customer Testing ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14261A1502014-09-17017 September 2014 Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M1 Diaphragms, Customer Testing ML14094A4452014-04-0101 April 2014 Notification of Part 21 Report on Defective Raw Material Used to Manufacture Valve Stems ML14069A4682014-03-0202 March 2014 Part 21 Report - Defective Raw Material Used to Manufacture Valve Stems ML14034A1892014-01-23023 January 2014 Part 21 - Loose Battery Vent Assemblies ML13211A1682013-07-26026 July 2013 Westinghouse, Notification of Potential Existence of Defects Pursuant to 10 CFR Part 21 Inconsistency Between the Intended Design Functionality of the Shield Passive Thermal Shutdown Seal (SDS) and That Observed During Post-Service Testing ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13073A1072013-03-12012 March 2013 Notification of Potential Part 21 Report - Defective Raw Material Used to Manufacture Valve Stems ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML13045A8932013-02-0101 February 2013 Notification of Part 21 Report - Defective Raw Material Used to Manufacture Valve Stems 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 ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML1005129082010-02-12012 February 2010 Notification of Potential Part 21 Report Re Interim Report Concerning an Issue in Sump Blockage Generic Tests ML1004801382010-02-12012 February 2010 Interim Report of the Evaluation of a Deviation Pursuant to 10CFR21.21(a)(2) 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 ML0713703092007-03-0707 March 2007 Velan, Inc., Piston Check Cv Information ML0627702242006-09-27027 September 2006 Part 21 Report from Tyco Valves & Controls LP, Improper Valve Springs in Pressure Relief Valves ML0626204942006-09-15015 September 2006 Part 21 Report by Tyco Valves and Controls, LP Re Improper Valve Springs in Pressure Relief Valves. Corrective Actions Taken by Tyco Listed ML0413205472004-04-23023 April 2004 Deficiency Report Re Potential Safety Hazard That Exists for Woodward Digital Reference Unit (Drus) 2024-09-06
[Table view] Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) 2024-09-06
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CURTISS-WRIGHT 4600 East Tech Drive Cincinnati, Ohio 45245 (5 I 3) 528-7900 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
SUBJECT:
10 CFR PART 21 REPORT REGARDING DISPOSITION OF A NONCONFORMANCE ON STRUTHERS-DUNN RELAY PART NUMBER B255XCXP125V FOR PSEG NUCLEAR LLC.
Event No.: ML16162A679 The attachment to this letter provides a report in accordance with I 0 CFR 21.21 pertaining to a potential deviation associated with Struthers-Dunn relays PIN B255XCXPI25V supplied to PSEG Nuclear LLC.
A copy of the report will be mailed to our affected nuclear customers.
If you have any questions pertaining to this information, please contact Timothy Franchuk, Director of Quality Assurance, at 513-20 l-2176.
Sincerely, Timothy Franchuk Director, Quality Assurance Nuclear Division Curtil)s-Wright cc: Regional Administrator, USNRC, Region III
Attachment to Letter Dated July 7, 2016 Page I of2 I 0 CFR PART 2 I REPORT REGARDING DISPOSITION OF A NONCONFORMANCE ON STRUTHERS-DUNN RELAY PART NUMBER B255XCXP125V FOR PSEG NUCLEAR LLC This report is being provided as a final report in accordance with I 0 CFR 2 I .21 (i) Name and address of the individual or individuals information the Commission.
Timothy Franchuk Director, Quality Assurance Nuclear Division Curtiss-Wright 4600 East Tech Drive, Cincinnati, OH 45245 (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.
Struthers-Dunn Relay PIN: B255XCXP125V. Note that the original interim report identified the part number as B255XCXPFHSC125V, which contains designators "FHSC", which are an internal Curtiss-Wright numbering scheme.
(iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
Curtiss-Wright, Nuclear Division.
(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.
PSEG has reported a failure of the reset coil within the Struthers-Dunn relay.
(v) The date on which the information of such defect or failure to comply was obtained.
The discovery date of the deviation that requires evaluation is April 8, 2016, based on the date PSEG alerted Curtiss-Wright of the potential defect within the reset coil (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.
Address Address PSEG Nuclear LLC Wolf Creek Generating Station Nuclear Business Unit 1550 Ox.en Lane, N.E.
Materials Center Wolf Creek Generating Station Alloway Creek Neck Road Hancocks Bridge, NJ 08038 Total Quantity: I 04 Total Quantity: 10
Attachment to Letter Dated July 7, 2016 Page 2 of2 vii) The evaluation and 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.
Evaluation: Findings as a result of the Curtiss-Wright Failure Analysis indicated that the reset coil failure was linked to the magnet wire insulation, the coil winding process, and the attachment of the coil leads to the magnet wire Corrective Action: Struthers-Dunn has revised their reset coil assembly procedure such that the reset coil receives two wraps of insulation tape prior to laying the magnet wire tenninations which are then soldered to the relay leads which connect to the pins at the base of the relay. Based on testing by Struthers-Dunn this two wrap process greatly increases dielectric strength which should eliminate the failure modes identified. Affected relays were returned to Struthers-Dunn to have the reset coil replaced using the revised reset coil assembly method. After the coils have been replaced they are sent to Curtiss-Wright Nuclear Division to be re-dedicated prior to being returned to the end
- user, (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 observed failures are believed to be attributed to a cumulative effect from discrepancies noted in the coil's magnet wire insulation, the coil winding process, and human error during fabrication. Since the failures could not be traced back to a specific, single issue, there is no specific test that could be developed I employed to filter for this failure. Currently there have been only three confirmed failures, all with one specific reset coil model (125VDC) and one specific date code (1526). As no one specific issue could be identified as the root cause, Curtiss-Wright has conservatively established a time frame of concern as January l st 2015 to May 31st 2016. This brackets reset coils made approximately six months prior to the failed date code up to the official date of the process change made by Struthers-Dunn. Purchasers are being advised to conduct their own evaluation to determine if a defect, which could create a substantial safety hazard, exists.