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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24057A3372024-02-25025 February 2024 56992-EN 56992 - Fairbanks Morse Defense ML24088A1142024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Report 23-02 Re Synchro-Start Mini-Gen Signal Generator ML24088A1102024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves ML24057A3382024-02-25025 February 2024 EN 56993 - Fairbanks Morse ML22087A0092022-03-0909 March 2022 Ultra Energy, Report Under 10CFR21 of Noncompliance for N7030 Transmitter 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 ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19248B7662019-08-0808 August 2019 Aaf Flanders - Event Number 5346, Reported at 2048 Est on 06/20/18 Re Unapproved Design Change in High Efficiency Particulate Air Filter ML18344A0542018-12-0606 December 2018 Framatome, Inc., 10 CFR Part 21 Notification of Existence of a Defect Involving O-ring Supplied in Chesterton Pump Seal Cartridge ML18313A0332018-10-31031 October 2018 Aaf International, Letter Regarding Unapproved Design Change in a High Efficiency Particulate Air Filter, Reported at 2048 Est on 06/20/18 ML18274A0162018-09-14014 September 2018 Aaf Flanders - Unapproved Design Change in a High Efficiency Particulate Air Filter ML18219A0082018-08-0606 August 2018 Follow-up to Interim Report of a Deviation or Failure to Comply ML18173A2742018-06-20020 June 2018 Aaf Flanders - Part 21 Report Re Unapproved Design Change in a High Efficiency Particulate Air Filter L-PI-17-037, Initial Notification of Failure to Comply or Existence of a Defect2017-09-14014 September 2017 Initial Notification of Failure to Comply or Existence of a Defect 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 L-PI-16-089, Interim Report of a Deviation or Failure to Comply2016-11-0404 November 2016 Interim Report of a Deviation or Failure to Comply ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16188A3782016-06-24024 June 2016 Part 21 - Deviation for Class 1E Solid State Relays (47H and 60Q) ML16162A6822016-06-0606 June 2016 Part 21 Notification - Deviation of K-Line Circuit Breaker Secondary Trip Latch ML16162A6812016-06-0606 June 2016 Part 21 - Notification of Deviation of K-Line Circuit Breaker Secondary Trip Latch 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 L-PI-15-074, Part 21 Notification of Failure to Comply or Existence of a Defect Affecting a Basic Component2015-09-0303 September 2015 Part 21 Notification of Failure to Comply or Existence of a Defect Affecting a Basic Component L-PI-15-069, Notification of Part 21 Report - Abb 50H Instantaneous Over Current Protection Relay Failure2015-08-0606 August 2015 Notification of Part 21 Report - Abb 50H Instantaneous Over Current Protection Relay Failure ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring 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 ML14094A4452014-04-0101 April 2014 Notification of Part 21 Report on Defective Raw Material Used to Manufacture Valve Stems ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13086A2552013-03-25025 March 2013 Part 21 Report - Foreign Material Inside EDG Air Start Piping ML13095A0112013-03-25025 March 2013 Update to Event Number 48798: 10 CFR Part 21 Notification, Dual Alarm Modules and Single Alarm Modules ML13079A3202013-03-18018 March 2013 Notification of Potential Part 21 Interim Report Re Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters 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 ML12283A2462012-09-28028 September 2012 Part 21 - Fairbanks Morse Opposed Piston EDG Oil Pump Leak ML12075A1062012-03-14014 March 2012 Notification of Potential Part 21 Re Defect on Arvan Electrical Terminal Blocks ML1104601222011-02-15015 February 2011 Fm Notification of Potential Part 21 Report Serial Number 10-06 Re Identification of Facilities within the Us Which Fails to Comply or Contains a Defect ML0932200662009-11-16016 November 2009 Part 21 Notification - Potential Failure in Emergency Diesel Generator Bearings ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs 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 ML0727504702007-09-21021 September 2007 MPR Associates, Inc. - Report of Defect in Accordance with 10 CFR 21 ML0710101252007-04-0909 April 2007 Fairbanks Morse Engine, Part 21 Notification - Diesel Cam Roller Bushing Failures 2024-02-25
[Table view] Category:Letter type:L
MONTHYEARL-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-10-21021 October 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024 Post-Submittal Package Letter L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024 – Preparation and Scheduling of Operator Licensing Examinations L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024 Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024 License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption L-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024 Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2) L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024 Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-027, Revision to 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2023-10-0303 October 2023 Revision to 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-23-025, License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-09-28028 September 2023 License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 L-PI-23-023, Baffle Former Bolts Alternate Aging Management Strategy2023-09-11011 September 2023 Baffle Former Bolts Alternate Aging Management Strategy L-PI-23-018, License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT2023-07-14014 July 2023 License Amendment Request to Revise ISFSI Technical Specification 4.4 to Allow Use of a Code Alternative to ASME Code, NB-5130, Examination of Weld Edge Preparation Surfaces, for the TN-40HT L-PI-23-006, License Amendment Request to Revise Technical Specification 3.7.8 Required Actions2023-06-22022 June 2023 License Amendment Request to Revise Technical Specification 3.7.8 Required Actions L-PI-23-016, 2022 10 CFR 50.46 LOCA Annual Report2023-06-14014 June 2023 2022 10 CFR 50.46 LOCA Annual Report L-PI-23-010, Annual Report of Individual Monitoring2023-04-27027 April 2023 Annual Report of Individual Monitoring L-PI-23-007, Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2023-03-28028 March 2023 Supplement to Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-23-005, CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2023-03-0303 March 2023 CFR 50.55a Requests Nos. 1-RR-5-15 and 2-RR-5-15, Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv) L-PI-23-001, Day Steam Generator Tube Inspection Report2023-01-30030 January 2023 Day Steam Generator Tube Inspection Report L-PI-22-047, Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report2022-12-21021 December 2022 Resubmittal of Prairie Island Nuclear Generating Plant (PINGP) 2018 Unit 1 180-Day Steam Generator Tube Inspection Report L-PI-22-020, Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2022-12-0202 December 2022 Application to Revise Technical Specification Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) L-PI-22-040, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0606 October 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-037, Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts2022-09-20020 September 2022 Updated Approach for Prairie Island Unit 1 and Unit 2 Baffle Former Bolts L-PI-22-032, CFR 50.46 LOCA Annual Report2022-06-16016 June 2022 CFR 50.46 LOCA Annual Report L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles L-PI-22-003, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-06-0707 June 2022 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections L-PI-22-024, Supplement to Application for License Amendment to Implement 24-Month Operating Cycle2022-03-0707 March 2022 Supplement to Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-029, Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.12021-10-0707 October 2021 Exigent License Amendment Request to Revise Technical Specification 3.7.8 to Allow a One-Time Extension of the Completion Time of Required Action B.1 L-PI-21-006, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions2021-10-0202 October 2021 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Incorporate Installed Bypass Test Capability for the Power Range RTS Functions L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-21-016, Application for License Amendment to Implement 24-Month Operating Cycle2021-08-0606 August 2021 Application for License Amendment to Implement 24-Month Operating Cycle L-PI-21-027, 2020 10 CFR 50.46 LOCA Annual Report2021-06-28028 June 2021 2020 10 CFR 50.46 LOCA Annual Report L-PI-21-023, Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report2021-05-14014 May 2021 Independent Spent Fuel Storage Installation - 2020 Annual Radiological Environmental Monitoring Program Report L-PI-21-007, Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes2021-04-19019 April 2021 Application to Revise Technical Specifications to Adopt TSTF-471, Eliminate Use of the Term Core Alterations in Actions and Notes L-PI-20-050, Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic2020-10-0707 October 2020 Request for a One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements, Due to COVID-19 Pandemic L-PI-20-051, Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2020-09-28028 September 2020 Supplement to Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-035, = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule2020-07-28028 July 2020 = Request for Revision to Reactor Vessel Material Surveillance Capsule Removal Schedule L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) L-PI-20-014, Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI2020-04-29029 April 2020 Supplement to License Amendment Request: Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI L-PI-20-004, License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.132020-03-30030 March 2020 License Amendment Request to Revise Technical Specifications (TS) to Remove Note I from Limiting Condition for Operating (LCO) 3.4.12 and LCO 3.4.13 L-PI-20-001, License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-12020-01-29029 January 2020 License Amendment Request to Address Issues Identified in Westinghouse Nuclear Safety Advisory Letter NSAL-09-5, Revision 1, and NSAL-15-1 L-PI-19-041, Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements2019-12-23023 December 2019 Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements L-PI-19-031, License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2019-12-16016 December 2019 License Amendment Request: Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-PI-19-040, License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency2019-10-0707 October 2019 License Amendment Request: Revise Technical Specification 5.5.14 to Permanently Extend Containment Leakage Rate Test Frequency 2024-08-23
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1717 Wakonade Drive Welch, MN 55089 Xcel Energy 800.895.4999 RESPONSIBLE BY NATURE xcelenergy.com L-PI-17-037 10 CFR 21.21 (d)(3)(i)
SEP 14 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Prairie Island Nuclear-Generating Plant Unit 2 Docket 50-306 Renewed License No. DPR-60 Initial Notification of Failure to Comply or Existence of a Defect Pursuant to 10 CFR 21.21 (d)(3)(i) Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), submits the attached initial notification of failure to comply or existence of a defect.
If there is any question or if any additional information is needed, please contact Frank Sienczak, at 651-267-1740.
Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.
Scott Northard Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company- Minnesota Attachment cc: Regional Administrator, Region Ill, USNRC Project Manager, Prairie Island Nuclear Generating Plant, USNRC Resident Inspector, Prairie Island Nuclear Generating Plant, USNRC
Attachment Initial Notification of Failure to Comply or Existence ofa Defect Name and Address of the Individual or individuals or informing the Commission:
Scott Northard Site Vice President Prairie Island Nuclear Generating Plant (PINGP)
Northern States Power Company- Minnesota 1717 Wakonade Drive East Welch, MN 55089 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:
Wartsila North America 16330 Air Center Boulevard Houston, Texas 77032 Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect:
Address on original purchase order: Address on current Qualified Supplier List:
Wartsila France Wartsila 1 Rue De La Fonderie 100 Quai d'Aiger Boite Postale 1210 cs 91210 Mulhouse Cedex, France Mulhouse Cedex, France 68054 68054 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:
On July 17, 2017, during the performance of SP 2305, D6 Diesel Generator Monthly Slow Start Test (WO 700015483), Operations received and responded to annunciator 47524-0706, D6 Diesel Generator Lockout Alarm.
Troubleshooting efforts found that the D6 Emergency Diesel Generator (EDG)
- trip and lockout event was caused by the D6 Engine 1 high crankcase pressure trip-switch being actuated with no high crankcase pressure trip condition present.
This was caused by pressure switch 2PSH-6169 "D6 Engine 1 Crank Case Pressure High" having a loose switch assembly. This resulted in an unwarranted I inadvertent trip of the D6 EDG, failure of SP 2305 and entry into an unplanned Technical Specification condition.
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Attachment Initial Notification of Failure to Comply or Existence of a Defect The mounting bracket fastener system failed due to fretting wear between the housing internal threads and the flat-head machine screws external threads. The loss of thread engagement from material wear resulted in a stripped condition.
The date on which the information of such defect or failure to comply was obtained:
July 17, 2017.
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:
Five pressure switches are on the PINGP site:
- One spare not installed in plant.
o (Wartsila/SACM Part number OLT360225 (switch- position detector of the crankcase overpressure detector sub-assembly) and Prairie Island Station CAT 10 number 255754)
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:
PINGP entered the 06 Oiesellockout trip into the Corrective Action Program. An extent of condition was performed on all skid mounted switches for loose mounted assemblies that could result in the actuation of a switch under false conditions. Results of the extent of condition review did not reveal relevant findings of loose mounted assemblies that feed the EOG Lockout Relay. PINGP also, performed a past operability review and determined that there was no firm evidence that indicated that the condition that closed the trip-switch contacts existed prior to the machine trip that occurred on July 17, 2017. Using the site's procedure for Past Operability Evaluations, the 06 EOG was not inoperable during the time period under review.
05 EOG was run within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the 06 EOG lockout to ensure operability of the available EOG. This satisfied "Common Cause" requirements.
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Attachment Initial Notification of Failure to Comply or Existence of a Defect PINGP notified the supplier of the inadvertent trip of 06 EDG and the loose mount assembly of pressure switch 2PSH-6169 on July 17, 2017.
Corrective actions being taken to address the cause include the installation of longer fasteners with the application of Loctite for added assurance. A torque value will also be specified for this application to maintain consistency and control among the four switch locations. The longer screws, known torque value, and thread locker will ensure preload is maintained to prevent premature switch failure.
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 pressure switches mounting assembly should be reassembled with longer screws, Loctite and proper torque value. Also the cable connected to the switch must be fixed on its dedicated holder.
In the case of an early site permit, the entities to whom an early site permit was transferred:
Not applicable.
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