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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARNL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers ML22307A0602022-11-0303 November 2022 EN 56200 - Fairbanks Morse Re Basic Component Which Fails to Comply or Contains a Defect ML20028D3802020-01-13013 January 2020 10CFR21 Notification for Ashcroft 2-1/2 & 3-1/2 1009, 63mm 2008, 63mm & 100mm 1008 Industrial Gauges, Weksler 3-1/2 Regal Gauges ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) 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 ML19158A1312019-05-31031 May 2019 Paragon Energy Systems LLC -10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML17340A3922017-11-28028 November 2017 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0119, Rev. 0 ML17333A3792017-11-21021 November 2017 Engine Systems, Inc. 10 CFR 21 Reportable Notification on a Power Supply (P/N 2938604) 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 ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling 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 ML16251A0982016-09-0202 September 2016 Part 21 - Potential Failure of Battery System Connections ML16139A8322016-05-13013 May 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16139A8332016-05-13013 May 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16125A3602016-04-26026 April 2016 Part 21 - Hydraulic Snubber Seal Material Deviation Interim Report ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15089A4372015-03-20020 March 2015 Part 21 - Dual Alarm Modules That May Contain Faulty Diodes in Single State Relays ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification 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 ML14169A0302014-06-15015 June 2014 Update to Interim Report - 10CFR 21 Evaluation Regarding Potential Deficiencies in Seismic Qualifications for PV-62 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 ML14071A4772014-02-26026 February 2014 Report of Potential Defect Per 1OCFR Part 21 Primary Disconnect Assembly ML14069A4672014-02-26026 February 2014 Part 21 Report Involving a Potential Manufacturing Defect in Replacement Masterpact Cradles ML13238A2532013-08-21021 August 2013 Notification of Potential Part 21 Report - Foxboro Power Supply Potential Failures Due to Defective the Wraps and Holders 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 ML13093A1532013-04-0202 April 2013 Part 21 Report - Foxboro Power Supply Potential Failures Due to Defective Tie Wraps and Holders ML13092A1182013-03-29029 March 2013 Notification of Potential Part 21 Interim Report on the Failure of an Emergency Diesel Generator Excitation System ML13073A1072013-03-12012 March 2013 Notification of Potential Part 21 Report - Defective Raw Material Used to Manufacture Valve Stems ML13063A4432013-03-0101 March 2013 10 CFR Part 21 Report Notification, Dual Alarm Modules and Single Alarm Modules ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve 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 ML12318A0412012-11-0808 November 2012 Part 21 Report - Commercial Grade Dedication Not Properly Applied to Butterfly Valves ML12283A2432012-10-0505 October 2012 Part 21 - Steam Generator Tube Wear Adjacent to Retainer Bars ML12283A3022012-10-0505 October 2012 Part 21 Report Re Steam Generator Tube to Tube Wear Identified at San Onofre Nuclear Generating Station ML12283A2462012-09-28028 September 2012 Part 21 - Fairbanks Morse Opposed Piston EDG Oil Pump Leak ML12255A0542012-09-0707 September 2012 Part 21 - Steam Generator Tube Wear Adjacent to Retainer Bars ML12255A0532012-09-0707 September 2012 Part 21 Interim Report - Steam Generator Tube Wear ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12157A3112012-06-0404 June 2012 Part 21 - Steam Generator Tube Wear Adjacent to Retainer Bars ML12157A3102012-06-0404 June 2012 Part 21 Interim Report - Steam Generator Tube Wear ML12121A5132012-04-19019 April 2012 Interim Report of Evaluation of a Deviation Pursuant to 10 CFR 21.21(a)(2) ML12121A5092012-04-19019 April 2012 Mitsubishi Nuclear Energy Systems, Part 21 Interim Report - Steam Generator Tube Wear ML12109A0942012-04-13013 April 2012 Part 21 Interim Report - Steam Generator Tube Wear ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations 2023-12-15
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0511312010 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Pakle I General Information or Other (PAR) Event# 45921 Rep Org: DRESSER-RAND Notification Date I Time: 05/12/2010 18:39 (EDT)
Supplier: DRESSER RAND Event Date / Time: 05/12/2010 (EDT)
Last Modification: 05/12/2010 Region: 1 Docket #:
City: WELLSVILLE Agreement State: Yes County: License #:
State: NY NRC Notified by: JOE MENICHINO Notifications: KATHLEEN O'DONOHUE R2DO HQ Ops Officer: CHARLES TEAL GREG PICK R4DO Emergency Class: NON EMERGENCY PART 21 GROUP EMAIL 10 CFR Section:
21.21 UNSPECIFIED PARAGRAPH LUGS ON DIGITAL FILTER IMPROPERLY SOLDERED A faulty Digital Control System Output Filter was discovered at Farley Nuclear Power station while installing it on the emergency feedwater Terry Steam Turbine. The problem only affects two plants: Farley Nuclear Power Station and San Onofre Nuclear Power Station. Farley replaced the filter before use. San Onofre had installed and used the filter, but they are replacing it.
"Description of Defect:
"Eyelets inserted into the printed circuit (p.c.) board to make connections from one side of the board to the other side were not soldered on the top side where the terminal block is installed. This may result in the connection being broken during tightening of the wire lug on the terminal block or if other stresses are applied to the p.c. board or terminal block. This defect is limited to output filter serial numbers 10009, 10010, 10011, and 10012.
"Engineering Evaluation and Recommendations:
"Failure can occur during assembly. The results of a seismic event are unknown. All 4 filters must be recovered and repaired. Locations of the 4 filters include Dresser-Rand, Farley Nuclear Station, and San Onofre Nuclear Generating Station."
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DRESSERRAND Wellsville Operations 37 Coats Street P.O. Box 592 Wellsville, NY 14895 PH: 585-593-1234 May 11, 2010 To: NRC Operations Center Fax: 301-816-5100
Subject:
10CFR Part 21 Initial Report Dresser-Rand No. 042 To Whom It May Concern-Attached find a copy of Dresser-Rand Initial Part 21 Report Number 042. It is directed at a Digital Control System Output Filter. The anomaly was recently discovered during an outage at the Farley Nuclear Power station. The plant was installing Dresser-Rand's Digital Control System Conversion on the Emergency Feedwater Terry Steam Turbine.
The problem is contained and the only 2 affected plants are Farley Nuclear Power Station and San Onofre Nuclear Power Station. Both plants have been notified of the issue and are implementing corrective action.
The Final Report will be issued by Dresser-Rand during the week of 5/17/2010.
Please call me at 585-596-3406 if there are any questions related to this issue.
Joe Menichino
_K Manager, Navy/Nuclear Product Engineering Dresser-Rand Government Business Unit 2/T'd 8226etkdooTsTeTg2T8:0i lINl 'sfl no9~:womj dt2:tP0 oTo2-2T-Aljiw
INITIAL REPORT 10CFR PART 21 REPORT OF.A POTENTIAL SAFETY HAZARD Report No. 042 Page 1 of I PREPARED BY: Mark Konieczny Date: 5/12/10 File No: F37858A/B TITLE: Navy Nuclear Product Engineer Serial No: T37858ANB Type: GS2N PART NAME: Output Filter Network Part No: 890313-001 Dwg. No: 890313 Rev. Level: N/A DEFECT:
DESCRIPTION OF Eyelets inserted into the p.c. board to make connections from one side of the board to the other side were not soldered on the top side where the terminal block is installed. This may result in the connection being broken during tightening of the wire lug on the terminal block or if other stresses are applied to the p.c. board or terminal block. This defect is limited to output filter serial #s 10009, 10010, 10011, and 10012.
ENGINEERING EVALUATION & RECOMMENDATIONS:
Failure can occur during assembly. Results of a seismic event are unknown. All 4 filters must be recovered and repaired. Locations of the 4 filters include Dresser-Rand, Farley Nuclear Station, and San Onofre Nuclear Generating Station.
Evaluation/Recommendation Prepared By: Mark Konieczny !4'( J /,F/
Title:
Navy Nuclear Produc-..lngineer E~ate: 212/1 t-(, I Approved By: Joe Menichino xvlzxo
Title:
Navy Nuclear Ergingefing Manager Date: 5/12/10 DISPOSITION, CHECK ONE:
^ Yes, this constitutes a safety hazard and requires a Final Report be prepared (EF-066)
- No, this does not constitute a safety hazard and does not require any further reporting.
Reviewed by D-R Wellsville
Signature:" .* .k--
Title:
Director Government Business Unit Date: __\ \--A)
RETURN TO MANAGER NUCLEAR PRODUCT ENGINEERING EF-065 (Initial Report 10 CFR Part 21 Report of a Potential Safety Hazard), REV. E, 16MAY01 2/2'd 92)_G2td00TS9T8T02T8:01 GT=%sTseg*8 ~T~9E~TB~dT2:tB0 0T02-2T-AUW IIfl 'sfl *OO:WcJýIA 2~2J9E!E2kd~T~TT0E8:oI