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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML22087A0092022-03-0909 March 2022 Ultra Energy, Report Under 10CFR21 of Noncompliance for N7030 Transmitter 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 ML20024E2552020-01-0909 January 2020 Engine Systems, Inc., Submittal of Selenium Surge Suppressor, Emo P/N 8403049 ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19199A0342019-07-0505 July 2019 Lake Engineering Co., Third Interim Notification Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. ZJS1518 ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19158A1302019-05-31031 May 2019 Curtiss-Wright Nuclear Division - Notification Report for Potential Part 21 Update ML19168A0102019-05-31031 May 2019 Curtis-Wright Nuclear Division- Notification Report for Potential Part 21 Update ML19168A0122019-05-31031 May 2019 Paragon Energy Solution LLC-10 CFR Part 21 Report of Defect GS2 Terry Turbine Introl Positioners ML19078A0872019-03-0808 March 2019 Curtiss-Wright - Interim Notification Report for Potential Part 21 Update ML19077A0962019-03-0505 March 2019 Interim Notification Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. ZJS1518 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 ML17243A1362017-08-28028 August 2017 Fisher Information Notice, (FIN) 2017-04 - Erroneous Rotary Seating Torque Calculation in Flowscanner Software ML17223A2002017-08-0909 August 2017 10 CFR Written Notification for Hex Head Cap Screws Nova Machine Products Part Numbers: BPRT.008227.30, BPRT.008468.30, and BPRT.008342.30 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 ML17104A2882017-04-13013 April 2017 Emerson Process Management, LLC - Fisher Information Notice, (FIN) 2017-02 ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards ML17114A0712017-04-13013 April 2017 10 CFR Part 21 Notification of Deviation - Gkt Relay 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 ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16281A2712016-09-30030 September 2016 Part 21 - Safety Related Component Welding by an Unqualified Welder ML16251A0982016-09-0202 September 2016 Part 21 - Potential Failure of Battery System Connections ML16243A4752016-08-26026 August 2016 Part 21 Safety Related Component Welding by an Unqualified Welder ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance 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 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 ML16039A2692016-02-0303 February 2016 Nutherm International, Inc. - Potential Issue Regarding Incorrect Industrial Irradiation Dose, Per Cooper, Oconee, Fitzpatrick, Point Beach, Brunswick, and Susquehanna 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 ML15259A5212015-09-10010 September 2015 Part 21 Report - Potential Failure of Electromatic Relief Valve Cutout Switches 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 ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring 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 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 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 ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14197A3802014-07-14014 July 2014 Part-21 Notification-Assembly Errors During Breaker Refurbishment ML14105A0182014-04-11011 April 2014 Part 21 - Model 1154HP Transmitters with Integral 1159 Remote Diaphragm Seals May Exhibit Degraded Functional Reliability ML14094A4452014-04-0101 April 2014 Notification of Part 21 Report on Defective Raw Material Used to Manufacture Valve Stems ML14072A3282014-03-13013 March 2014 Part 21 60-Day Interim Report Notification Re Unseating of Valve Spring on SSPV 2022-03-09
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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