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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23241A0022023-08-25025 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 ML23066A2212023-03-0707 March 2023 Velan, Inc. - Revised Part 21 Notification Re Butterfly Valves Found to Have a Number of Fasteners Loose ML23038A0192023-02-0606 February 2023 Curtiss-Wright Part 21 Notification for Qualtech Np Supplied Eaton TMR5 Timing Relays ML22341A0322022-11-30030 November 2022 10 CFR Part 21 Notification from Curtiss-Wright Nuclear Division for Qualtech Np Supplied Eaton TRM5 Timing Relays ML22307A0602022-11-0303 November 2022 EN 56200 - Fairbanks Morse Re Basic Component Which Fails to Comply or Contains a Defect ML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML22305A5152022-02-22022 February 2022 EN 56192 - Grand Gulf Nuclear Station Re Elevation Outer Containment Personnel Airlock Door Failed Its Technical Specification Leakage Test ML21322A0512021-10-27027 October 2021 Paragon Energy Solutions, LLC, P21-09282021, Rev. 0, Final Notification of a Deviation with Inverter Assembly (Model NLI-072034-CSI-K-5-A) ML21225A0812021-08-0404 August 2021 Lake Engineering Co., Final Report Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 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 ML21168A2172021-06-17017 June 2021 GE Hitachi Nuclear Energy Americas, LLC - 10 CFR Part 21.21(d)-Reportable Condition: Fuel Support Side Entry Orifice Meta-Stable Flow for 2 Beam Locations in the BWR/6 Reactors M210077, GE Hitachi Nuclear Energy Americas, LLC - 10 CFR Part 21.21(d)-Reportable Condition: Fuel Support Side Entry Orifice Meta-Stable Flow for 2 Beam Locations in the BWR/6 Reactors2021-06-17017 June 2021 GE Hitachi Nuclear Energy Americas, LLC - 10 CFR Part 21.21(d)-Reportable Condition: Fuel Support Side Entry Orifice Meta-Stable Flow for 2 Beam Locations in the BWR/6 Reactors ML21126A1722021-04-29029 April 2021 Paragon Energy Solutions Failures of Size 1 and 2 Freedom Series Full Voltage Reversing Starters ML21014A2342020-12-0707 December 2020 Fourth Interim Notification Per 10 CFR Part 21 Re Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML20366A0482020-12-0707 December 2020 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. 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Report No. 10CFR21-0129, Rev. 0, Test Stand Deficiency - EMD Fuel Injectors P/N H40084720 ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries 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 ML19253A0532019-08-29029 August 2019 Azz Nuclear - Report of Potential 1O CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors 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 ML19101A0972019-04-0404 April 2019 Weir Valves & Controls USA, Inc. Part 21 Written Notification - Event Number: 53973 - 24 Class 150 Globe Alve for RHRSW HX Isolation MOV, E1150F068B at Detroit Edison - Fermi, Unit 2, Experienced Two Stem Failures ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML19053A5002019-02-0101 February 2019 Sor, Inc. Part 21 Notification of Deviation Sor R-Series Housing with Terminal Block ML19002A2042018-12-21021 December 2018 to Engine Systems, Inc., Part 21 Report Re Emd Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18354A7422018-12-0404 December 2018 Engine Systems, Inc., Submittal of 1OCFR21 Reporting of Defects and Non-Compliance - Report No. 1OCFR21-0123, Rev. 0 - Emo Fuel and Soakback Pumps - Potentially Undertorqued Cover Bolts ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps 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) ML17313A4712017-11-0303 November 2017 Part 21 - Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Interim Report 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 ML17212A6282017-07-24024 July 2017 Lake Engineering Co. - Potentially Degraded Snubber SF1154 Hydraulic Fluid Second - Interim Notification Per 10 CFR Part 21 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 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 ML17081A4542017-03-17017 March 2017 Part 21 Notification - Evaluation of a Deviation - Starter Contactor Failure ML17055C1772017-02-0909 February 2017 10 CFR 21 Evaluation Regarding Design Basis Calculation Error Using FL0-2D Software ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML17032A0802016-12-30030 December 2016 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0114, Rev. 0 ML17006A0102016-12-29029 December 2016 Engine Systems, Inc. - Part 21 Issues Identified with the Enterprise Diesel Engine Subcover ML17006A0112016-12-13013 December 2016 Part 21 Notification - Defective Safety-Related Relays Supplied by TE Connectivity 2023-09-06
[Table view] Category:Letter
MONTHYEARIR 05000352/20243012024-02-0202 February 2024 Initial Operator Licensing Examination Report 05000352/2024301 and 05000353/2024301 IR 05000352/20240112024-01-31031 January 2024 Information Request to Support Post-Approval Site Inspection for License Renewal; Inspection Report 05000352/2024011 IR 05000352/20230042024-01-31031 January 2024 Integrated Inspection Report 05000352/2023004 and 05000353/2023004 ML24012A1422024-01-31031 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0051 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) GO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000440/20230042024-01-30030 January 2024 Integrated Inspection Report 05000440/2023004 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 IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 ML24026A2962024-01-26026 January 2024 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System (PPS)- Syrs, . IR 05000416/20230042024-01-25025 January 2024 Integrated Inspection Report 5000416/2023004 L-24-017, 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative2024-01-24024 January 2024 30-Day Voluntary Report in Accordance with Industry Groundwater Protection Initiative L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML24018A0222024-01-18018 January 2024 Core Operating Limits Report (COLR) Cycle 24, Revision 2 ML24004A0342024-01-17017 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0026 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000416/20243012024-01-16016 January 2024 NRC Initial Operator Licensing Examination Approval 05000416/2024301 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and IR 05000352/20230102024-01-11011 January 2024 Age-Related Degradation Report 05000352/2023010 and 05000353/2023010 ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information IR 05000440/20234022024-01-10010 January 2024 Cyber Security Inspection Report 05000440/2023402 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 ML24003A8032024-01-0303 January 2024 Notification of NRC Fire Protection Team Inspection Request for Information IR 05000352/20234012023-12-21021 December 2023 Cybersecurity Inspection Report 05000352/2023401 and 05000353/2023401 ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23321A0472023-12-20020 December 2023 Letter to Rod L. Penfield - Perry Nuclear Power Plant, Unit 1 - License Renewal Regulatory Audit Regarding the Environmental Review of the License Renewal Application GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium 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 GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection ML23348A3712023-12-14014 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report (05000416/2024011) and Request for Information ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23321A2362023-12-14014 December 2023 Issuance of Amendment Nos. 262 and 224 Adoption of TSTF-477, Revision 3 and Associated Technical Specification Changes ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23340A2222023-12-13013 December 2023 Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection 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 L-23-171, CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency2023-12-0808 December 2023 CFR 50.55a Request Number VR-9. Revision 0, Feedwater Check Valve Exercising Test Frequency ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-23-244, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23333A2182023-11-29029 November 2023 Operator Licensing Examination Approval 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 IR 05000440/20230112023-11-28028 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000440/2023011 IR 05000440/20234032023-11-27027 November 2023 Security Baseline Inspection Report 05000440/2023403 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 ML23325A2062023-11-21021 November 2023 Supplement to License Amendment Request to Revise the Licensing and Design Basis to Incorporate the Replacement of Existing Safety-Related Analog Control Systems with a Single Digital Plant Protection System ML23325A1422023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 2024-02-02
[Table view] |
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pl 05/08/2014 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page I Part 21 (PAR) Event # 50096 Rep Org: SCIENTECH Notification Date I Time: 05/08/2014 14:57 (EDT)
Supplier: SCIENTECH Event Date I Time: 05/07/2014 (MDT)
Last Modification: 05/08/2014 Region: 4 Docket #:
City: IDAHO FALLS Agreement State: No County: License #:
State: ID NRC Notified by: VINCENT CHERMAK Notifications: JOHNATHAN LILLIENDAHL RIDO HQ Ops Officer: STEVE SANDIN KENNETH RIEMER R3DO Emergency Class: NON EMERGENCY JACK WHITTEN R4DO 10 CFR Section: NRR PART 21 EMAIL 21.21 (d)(3)(i) DEFECTS AND NONCOMPLIANCE PART 21 - POTENTIAL DEFECT IN NUS-710DU TRIP UNIT TO PRODUCE A VALID TRIP OUTPUT SIGNAL The following summary was provided by Curtiss-Wright Flow Control Corporation:
"In certain operating configurations, NUS-710DU Trip Units could fail to produce a valid trip output signal.
"Transistor Q8 on the referenced units uses a TO-66 package and is flush mounted on the component side of the PCB. The TO-66 package, based on JDEC drawing TO-213 does not specify the size of the glass-sealed holes in the case (collector) around the base and emitter leads. Random samples measure approximately 0.11" in diameter. The PCB includes standard 0.100" solder pads on both non-component and component sides. During manufacture, Q8 is secured using screws and nuts with leads centered in the through-holes, so no direct solder pad to case contact is possible. However, the presence of the pad on the component side could facilitate, under certain conditions, excessive solder flow, creating a close proximity, or in the extreme case bridging, between solder on the emitter or base solder pad and the Q8 case. Permanent bridging would be detected during acceptance testing. However, in at least one case, with the trip unit mounted in the trip unit chassis via an extender card, the proximity was close enough to create contact when the board was slightly flexed.
"The trip units have two modes of operation, NORM and REV, selectable by switch S2, and four operating configurations: (1) NORM mode, rising trip, energize on trip, (2) REV mode, falling trip, energize on trip, (3) NORM mode, falling trip, de-energize on trip and (4) REV mode, rising trip, de-energize on trip.
"In configuration (1), the set point is applied to the negative terminal of a comparator and the input is applied to the positive terminal. When the input rises above the set point, the output of the comparator goes to the positive rail, turning on Q7. When Q7 turns on, it pulls the base of Q8 low, causing Q8 to turn on. When Q8 turns on, the trip output goes to approximately +24V.
w 05/08/2014 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page 2 "In configuration (2), the set point is applied to the positive terminal of the comparator and the input is applied to the negative terminal. When the input drops below the set point, the output of the comparator goes to the positive rail and turns on Q8, resulting in a trip output of approximately +24V.
"In configurations (1) and (2), bridging at Q8 would cause an output trip signal.
"In configuration (3), when the input drops below the reset point, the output of the comparator goes to the negative rail, which causes Q8 to turn off. When Q8 turns off, the trip output goes to approximately zero volts.
"In configuration (4), when the input rises above the reset point, the output of the comparator goes to the negative rail and turns off Q8, de-energizing the unit output.
"In configurations (3) and (4), bridging at Q8 would prevent a valid trip signal from being generated by keeping the output at logic high.
"Plant: Limerick/Part Number: NUS-710DUOTS/Quantity: 2/Serial Numbers: 1303582, 1303583 "Plant: Limerick/Part Number: NUS-710DUOTT27000/Quantity: 6/Serial Numbers: 1304197, 1304198,1304199, 1304200,1304201,1304202 "Plant: Columbia/Part Number: NUS-710DUOTT45059/Quantity: 5/Serial Numbers: 1303632, 1303633, 1303634, 1303635,1303636 "Plant: Grand Gulf/Part Number: NUS-710DUOTT27000/Quantity: 3/Serial Numbers: 1303672, 1303673, 1303674 "Plant: Perry/Part Number: NUS-710DUOTT27000/Quantity: 33/Serial Numbers: 1304219, 1304220, 1304221, 1304222, 1304223, 1304224, 1304225,1304226,1304227,1304228,1304229,1304230,1304231, 1304232, 1304233, 1304234,1304235,1304236,1304237, 1304238, 1304239, 1304240,1304241, 1304242, 1304243, 1304244,1304245,1304246,1304247,1304248,1304249,1304250, 1304251.
"Should you have any questions regarding this matter, please contact Robert Queenan, Division Manager, Scientech/Instrumentation and Controls, at (208) 524-9311."
Inslnimentation & Controls Division RIGIdaho CU R 200 S. Woodruff Ave.
Falls, ID83401 (208) 529-1000 May 8"' 2014 Letter Number: AVC-14-005 Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject:
10 CFR Part 21 Report Notification, NUS71 ODU Trip Units
Dear Sir or Madam:
The purpose of this letter is to notify the Nuclear Regulatory Commission of a defect. In certain operating configurations, NUS-7 1ODU Trip Units could fail to produce a valid trip output signal. Details of the defect are provided below.
I-l" IL
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in 6dual AV Chermak Quality Manager Scientech, a business unit of Curtiss-Wright Flow Control Corporation 200 S Woodruff Avenue Idaho Falls, Idaho 83401 Dan Meils General Manager Scientech, a business unit of Curtiss-Wright Flow Control Corporation 29399 US Hwy 19 North, Suite 320 Clearwater, FL 33761 (it) idctiillcallon ac h :ila , 1t1 JClmmti . cmr 01 c 1)asic Cl111 0c 1.suppiliCd olwsuch (hcility Or such 3cti 1mpc )it'
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> J xIch N (w coin lwti1i a dIccfci hmiý;S hi cc1i111)In NUS-7 10DUOTT; A Master Trip Unit manufactured by Scientech.
NUS-7 1ODUOTS; A Slave Trip Unit manufactured by Scientech.
liii) hint'ilcaic;on i* Ir firm coin iract inu, fhic lalcihii3 c suppiyvinigI h1c basic collin)olcflt w hich tails to comply oi Scientech, a business unit of Curtiss-Wright Flow Control Corporation 200 S Woodruff Avenue Idaho Falls, ID 83401
Instrumentation & Controls Division CURTISS200 S. Woodruff Ave.
WRIGHT ,
Idaho Falls, ID 83401 (208) 529-1000
{iv) N;itult ot'flic dcicclt or Iailure to (oniply aild lhc salctI haard which is crcalcd or could bKcr-catled bY stluch dct'c*c o*r Iailurc, l* 'ouilv/t.
In certain operating configurations, NUS-710DU Trip Units could fail to produce a valid trip output signal.
E Glass seal around lead S Thru hole for solder fiow Transistor Q8 on the referenced units uses a TO-66 package and is flush mounted on the component side of the PCB. The TO-66 package, based on JDEC drawing TO-213 does not specify the size of the glass-sealed holes in the case (collector) around the base and emitter leads. Random samples measure approximately 0.11" in diameter.
The PCB includes standard 0.100" solder pads on both non-component and component sides. During manufacture, Q8 is secured using screws and nuts with leads centered in the through-holes, so no direct solder pad to case contact is possible. However, the presence of the pad on the component side could facilitate, under certain conditions, excessive solder flow, creating a close proximity, or in the extreme case bridging, between solder on the emitter or base solder pad and the Q8 case. Permanent bridging would be detected during acceptance testing.
However, in at least one case, with the trip unit mounted in the trip unit chassis via an extender card, the proximity was close enough to create contact when the board was slightly flexed.
The trip units have two modes of operation, NORM and REV, selectable by switch S2, and four operating configurations: (1) NORM mode, rising trip, energize on trip, (2) REV mode, falling trip, energize on trip, (3)
NORM mode, falling trip, de-energize on trip and (4) REV mode, rising trip, de-energize on trip.
In configuration (1), the set point is applied to the negative terminal of a comparator and the input is applied to the positive terminal. When the input rises above the set point, the output of the comparator goes to the positive rail, turning on Q7. When Q7 turns on, it pulls the base of Q8 low, causing Q8 to turn on. When Q8 turns on, the trip output goes to approximately +24V.
In configuration (2), the set point is applied to the positive terminal of the comparator and the input is applied to the negative terminal. When the input drops below the set point, the output of the comparator goes to the positive rail and turns on Q8, resulting in a trip output of approximately +24V.
In configurations (1) and (2), bridging at Q8 would cause an output trip signal.
In configuration (3), when the input drops below the reset point, the output of the comparator goes to the negative rail, which causes Q8 to turn off. When Q8 turns off, the trip output goes to approximately zero volts.
In configuration (4), when the input rises above the reset point, the output of the comparator goes to the negative rail and turns off Q8, de-energizing the unit output.
CURTISS - Instrumentation & Controls Division 200 S. Woodruff Ave.
WRIGHT Idaho Falls, ID 83401 (208) 529-1000 In configurations (3) and (4), bridging at Q8 would prevent a valid trip signal from being generated by keeping the output at logic high.
Submitted for evaluation 4/29/2014. The evaluation was completed on 5/7/2014 In tih ~.c 1a1 1/4nOl
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Plant Part Number Quantity Serial Numbers NUS-710DUOTS 2 1303582, 1303583 Limerick NUS-710DUOTT27000 6 1304197, 1304198, 1304199, 1304200, 1304201, 1304202 Columbia NUS-710DUOTT45059 5 1303632, 1303633, 1303634, 1303635, 1303636 Grand Gulf NUS-7 IODUOTT27000 3 1303672, 1303673, 1303674 1304219, 1304220, 1304221, 1304222, 1304223, 1304224, 1304225, 1304226, 1304227, 1304228, 1304229, 1304230, 1304231, 1304232, 1304233, Perry NUS-710DUOTT27000 33 1304234, 1304235, 1304236, 1304237, 1304238, 1304239, 1304240, 1304241, 1304242, 1304243, 1304244, 1304245, 1304246, 1304247, 1304248, 1304249, 1304250, 1304251
( I Ih 1CcI I I (l: t I)iI x Ih i%\Ih 1;1x bcct 1.1 'I I' IIIsiO ll*, w II h I kbe n ta ,ld Wico t hei in ilid uniI(m orI ;)lflh 111iOll 101-~K i u 16c1 lcflol. ;111(1 ht leIgth l 11111c,~ that ha~s hccni Or W~ill be t.akn io conipilei ilhe act ion.
- 1. Scientech has identified a design change that corrects the problem. The correction is to install spacers under Q8 to provide clearance from the board. The Design Change Notice was complete May 7, 2014.
- 2. Scientech has placed a hold on all affected in-house modules, and will incorporate the design change prior to ship.
- 3. Scientech will notify the plants listed per 21.21(d)(4)(vi) above, and offer to correct the affected units at Scientech's facility by close of business May 8, 2014.
CURTISSWRIGHT-Instrumentation & Controls Division 200 S. Woodruff Ave.
Idaho Falls, ID 83401 (208) 529-1000 1% iii) Any advice reiated to the defect or lhilure to comply about tlie rtcility. actli Iy. or basic Component dhat has hecin, is hci,, or will bc givei to ptrc hasers or licensees.
None.
(ix) III thC case okan1 earls site permit. the entities lo whom an Carly siic permit wa,, transte'rrcd Not applicable.
Should you have any questions regarding this matter, please contact Robert Queenan, Division Manager, Scientech/Instrumentation and Controls, at (208) 524-9311.
A Vincent Chermak, SSBB, PMP Quality Assurance Manager I&C Division Scientech, a business unit of Curtiss-Wright Flow Control Company Office (208) 524-9202 1Fax (208) 524-9238 Cc: Dan Meils Robert Queenan John McGimpsey Michael Weinstein QA File