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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24302A2772024-10-28028 October 2024 57243-EN 57243_5 - Rssc Dba Marmon - Update 20241030 ML17223A1982017-07-21021 July 2017 Part 21 Notification - Eaton/Cutler Hammer A200 Series Starter PLA-7613, Interim Report of a Deviation, Units 1 & 2 - (PLA-7613)2017-06-0909 June 2017 Interim Report of a Deviation, Units 1 & 2 - (PLA-7613) ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML11115A0392011-04-14014 April 2011 Notice of Deviation Pursuant to 10 CFR 21, NPKC-7-21A(N) Splice Kit with Possible Compromised Jacket Seal ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1018907392010-07-0101 July 2010 Part 21 Report Concerning Failure of Turbine Overspeed Reset Control Valve Diaphragm ML1015305642010-05-28028 May 2010 Part 21 Notification from C & D Technologies, Inc., Post Corrosion on Dcu Batteries ML1009604492010-04-0202 April 2010 Part 21 Report by Tyco Valves and Controls, LP Possible Failure of Solenoid Valves with Dual Function Main Steam Safety Valves ML0934301402009-12-0202 December 2009 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 1OCFR21-0098, Rev. 0, Amot Thermostatic Valve Element, P/N: 9760X ML0232901622002-11-18018 November 2002 Final Report, Stability Option III: Possible Successive Confirmation Count Resets - Not Reportable ML18024A0581978-09-18018 September 1978 Letter Attaching a Final Report of a Deficiency in Carriage Bolt Fasteners Used on 480 Volt Motor Control Center Bus Splices ML18024A1011978-07-19019 July 1978 Letter Attaching a Report of Defects Discovered During Qualification and Manufacturing of Control Room Systems ML18024A0661978-07-14014 July 1978 Letter Referring to the April 17, 1978 Letter and Regarding an Update of Interim Report of Reportable Deficiency Regarding Potential Transformers on 4.16K Switchgear ML18024A0681978-07-0505 July 1978 Letter Referring to the April 26, 1978 Letter and Advising the Commission That a Definitive Report Will Be Submitted by September 29, 1978 ML18024A0771978-06-23023 June 1978 Letter Referring to the June 22, 1977 Letter and Relating to the Definitive Report, Prepared by Bechtel Power Corp., of a Reportable Deficiency Regarding Unsatisfactory Field Welding and Inspection of Shear Suds ML18024A0691978-05-31031 May 1978 Letter Referring to the December 1, 1977 Letter Providing an Interim Report of a Deficiency in Physical Separation of Electrical Circuits and Advising the Commission That the Definitive Report Will Be Submitted by September ML18024A0711978-04-26026 April 1978 Letter Attaching Bechtel Engineering'S Interim Report on Spot Welding of Struts for SSES Units 1 and 2 and Advising the Commission That the Definitive Report Will Be Submitted by July 31, 1978 ML18025A4791976-11-0505 November 1976 Interim Report of Reportable Deficiency Defect in RPV Susquehanna Unit 2 Bottom Head Side Plate ML18025A4901975-08-29029 August 1975 Letter Regarding the Definitive Report of Deficiencies in Box Column Supports Which Supplements PLA-74 ML18025A4921975-04-0404 April 1975 Letter Attaching an Interim Report on Potential Deficiency Which Was Discussed with Mr. Heishman on March 6, 1975 2024-10-28
[Table view] 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 ML23279A0612023-10-0505 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) ML23094A1252023-03-31031 March 2023 Talen Part 21 Final Notification P21-03032023-FN R0 Re Defect Identified in Automatic Transfer Switch ML23094A1242023-03-31031 March 2023 EN 56387 Update - Paragon Energy Solutions Final Notification of Defect of Automatic Transfer Switch ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 ML20073G4572020-03-0909 March 2020 Carrier Corporation - Final Report Notification of Defect Pursuant to 10 CFR Part 21 for 17FA999-1200-107 Oil Pump ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19120A1062019-04-17017 April 2019 Interim Report of Potential 10 CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML18087A0022018-03-21021 March 2018 Crane Nuclear, Inc. - Final Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem 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) ML17311A9092017-10-31031 October 2017 Interim Report for Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem ML17223A1982017-07-21021 July 2017 Part 21 Notification - Eaton/Cutler Hammer A200 Series Starter ML17206A0402017-07-14014 July 2017 Part 21 - Defective Safety Related Valves PLA-7613, Interim Report of a Deviation, Units 1 & 2 - (PLA-7613)2017-06-0909 June 2017 Interim Report of a Deviation, Units 1 & 2 - (PLA-7613) ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 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 ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML16321A4502016-08-31031 August 2016 Part 21 Notification - Flowserve Swing Check Valves ML16039A2692016-02-0303 February 2016 Nutherm International, Inc. - Potential Issue Regarding Incorrect Industrial Irradiation Dose, Per Cooper, Oconee, Fitzpatrick, Point Beach, Brunswick, and Susquehanna ML15034A5662015-01-23023 January 2015 Notification of Potential Part 21 for Event #50703 ML15030A0332015-01-20020 January 2015 Letter from James Thigpen Notification of Potential Part 21 Nuclear Nonconformance Event Number 50703 ML14337A0942014-11-24024 November 2014 Notification of Potential Part 21 - Lack of Proper Power Supply Indication ML14329A0632014-11-19019 November 2014 Notification of Potential Part 21 Re Lack of Proper Power Supply Indication 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 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) ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14169A0302014-06-15015 June 2014 Update to Interim Report - 10CFR 21 Evaluation Regarding Potential Deficiencies in Seismic Qualifications for PV-62 ML14303A5262014-03-28028 March 2014 Interim Part 21 Report - Misaligned Separators in LCR-25 Standby Batteries ML13340A3822013-12-0505 December 2013 Part 21 Reportable Condition Notification: Failure of Relay Logic Card Modules in 2 Out of 4 Voters ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML12352A1232012-12-13013 December 2012 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML12348A1362012-12-13013 December 2012 Part 21 60-Day Interim Report Notification: Adequacy of Design Change in Am Magne-Blast Circuit Breakers ML12347A3082012-12-12012 December 2012 Part 21 60-Day Interim Report Notification: Error in Main Steam Line High Flow Calculational Methodology ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12040A2832012-02-0707 February 2012 Notification of Potential Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML12038A0282012-02-0202 February 2012 Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12032A2402012-02-0101 February 2012 Notification of Potential Part 21 - 60-Day Interim Report Notification: Failure of CRD Collet Retainer Tube/Outer Tube Weld ML11340A1002011-12-0505 December 2011 Letter 10 CFR Part 21 Notification Report, CON2000 and RTD2100 Spring Clips ML11341A0602011-12-0505 December 2011 Notification of Potential Part 21 Involving Defective Spring Clips Used as Seismic Restraints on Two Scientific Modules ML11363A1882011-12-0202 December 2011 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0098, Rev. 3, Amot Thermostatic Valve Element P/N: 9760X ML11336A3692011-12-0101 December 2011 Notification of Potential Part 21 Interim Report on Thermostatic Valve Failure on Palo Verde EDG ML11228A0842011-08-12012 August 2011 Notification of Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1122401422011-08-11011 August 2011 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance 2024-09-06
[Table view] |
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0712112017 U.S. Nuclear Regulatory Commission Operations Center Event Report ***Page I Part 21 (PAR) Event# 52867 Rep Org: SUSQUEHANNA NUCLEAR LLC Notification Date I Time: 07/21/2017 10:40 (EDT)
Supplier: EATON/CUTLER HAMfvlER Event Date I Time: 07 /14/2017 16:46 (EDT)
Last Modification: 07/21/2017 Region: 1 Docket#:
City: BERWICK Agreement State: Yes County: License#:
State: PA NRC Notified by: JASON JENNINGS Notifications: ANNE DeFRANCISCO R1DO HQ Ops Offi~er: VINCE KLCO PART 21/50.55 REACTORS EMAIL Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 (d)(3)(i) DEFECTS AND NONCOMPLIANCE PART 21 NOTIFICATION - EATON/CUTLER HAMMER A200 SERIES STARTER The following information was received by the licensee via email:
"Pursuant to 10 CFR 21, this is a non-emergency notification by Susquehanna Nuclear, LLC concerning a defect in an Eaton/Cutler Hammer A200 series starter that failed while in service at Susquehanna Steam Electric Station.
The failed starter was manufactured by Eaton Corporation in 2014 and purchased by Susquehanna from .AZZ/NLI as part of an MCC bucket assembly. The starter failed with its contacts stuck in the energized state when it was de-energized. A failure analysis identified the contactor sticking to be due to the pole faces of the coil laminations and those of the armature laminations adhering to one another at normal operating temperatures. There was residue/material on the pole faces which closely matched Polydimethylsiloxane (PDMS) and silicone grease. One of the characteristics of PDMS is. that at cooler temperatures it is more of a solid consistency, and at higher temperatures it becomes more viscous and tacky.
"A previous Part 21 report submitted by Curtiss-Wright QualTech NP (Event Notification 51611) in December 2015 provided notification of Eaton/Cutler Hammer A200 series starters failures due to silicon based mold release that remained on the molded parts and would come between the moving (magnet) and fixed armatures. The Part 21 stated that when heated for extended period of time, the material would become sticky causing anywhere from a minor delay in opening to a frozen closed condition. Eaton/Cutler Hammer determined that the silicone mold release was first introduced into the manufacturing facility in May 2008 and used periodically until October 2012. According to Eaton/Cutler Hammer, any starters manufactured after January 1, 2013 should be silicon mold release free.
"Following the failure of the 2014 starter at Susquehanna, Eaton Corporation performed an investigation and reconfirmed that silicon mold release was banned from molding production in October 2012 and has not been used
0712112017 U.S. Nuclear Regulatory Commission Operations Center Event Report P(lge 2_
since that time. Eaton concluded that the contamination does not appear to be systemic, but rather random and intermittent a'nd that the contamination was most likely introduced either by operators and assemblers on the manufacturing lines, or by others who disassemble and inspect the product after shipment from their plant.
Susquehanna does not take the components apart during receipt for testing or visual inspection. Eaton concluded that there is no evidence that the issue is systemic and considers it a random event. Susquehanna has evaluated the condition and has concluded that the condition could create a substantial safety hazard."
The licensee notified the NRC Resident Inspector.
From: Jennings. Jason To: Hoc. HOO X Cc: Hood. Tanya; Micewski. Laura
Subject:
[External_Sender] Susquehanna Part 21 Notification Date: Friday, July 21, 2017 10:35:50 AM Attachments: Susquehanna Part 21.pdf Please see attached for Part 21 Initial Notification from Susquehanna. I will follow up with a phone call shortly. Thank you -
Jason Jennings Nuclear Regulatory Affairs Manager Susquehanna Nuclear, LLC (570)542-3155 The information contained in this messag_e is intended only for the personal and confidential use of the recipient(s) namea above. If the reader of this message is not the intended recipient or an agent responsible for delivering it to the intended recipient, you are hereby notified that you have received this document in error and that any review, dissemination, distributron, or copying of this message is strictly prohibited. Ilyou have re~e.ived this communication in error, please notify us immediately, and delete the ongmal message.
1152PAGE 1OF2 NRCFORM361 U.S. NUCLEAR REGULATORY COMMISSION (12-2000) OPERAllONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN#
NRC OPERAllON TELEPHONE NUMBER: PRIMARY - 301-816-5100 or 800-532-3469*, BACKUPS *[1 Sl] 301-951-0550 or 800-449-3694*,
[2nd} 301415-0550 and [3rd] 301-415-0553 *Licensees who maintain their own ETS are provided these telephone numbers.
NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALLBACK#:
SUSQUEHANNA NUCLEAR LLC 2 Jason Jennings 570-542-3155 EVENT TIME & ZONE EVENT DATE POWERMODE BEFORE POWERMODE AFTER 1646 EDT 7/14/2017 U1: 100% I Mode 1/U2:100% I Mode 1 U1: 100% I Mode 1 / U2: 100% I Mode EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (V){A) Safe S/D Capability AINA GENERAL EMERGENCY GEN/AAEC I TS Deviation ADEV (v)(B} RHR Capability AINB SITEAREAEMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR50.72(b)(2) (v)(C) Control of Rad Release AINC ALERT ALE/AAEC (Q TS Required S/D ASHU {v)(D) Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC {iv)(A) ECCS Discharge to RCS ACCS {XII) Offsite Medical AMED 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss Comm/AsmUResp ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Offiste Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)
MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG other Unspecified Requirement (Identify)
OTHER UNSPECIFIED REQMT (see last column) (ii)(B) Unanalyzed Condition AUNA x 10 CFR 21.21(d)(3)(i) NONR INFORMATION ONLY NNF (lv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected, actuations & their initiating signals, causes, effect of event on plant, actions taken or planned, etc. (Continue on back)
Part 21 Notification - Eaton/Cutler Hammer A200 Series Starter Pursuant to 10 CFR 21, this is a non-emergency* notification by Susquehanna Nuclear, LLC concerning a defect in an Eaton/Cutler Hammer A200 series starter that failed while in service at Susquehanna Steam Electric Station. The failed starter was manufactured by Eaton Corporation in 2014 and purchased by Susquehanna from AZZ/NLI as part of an MCC bucket assembly. The starter failed with its contacts stuck in the energized state when it was de-energized. A failure analysis identified the contactor sticking to be due to the pole faces of the coil laminations and those of the armature laminations adhering to one another at normal operating temperatures. There was residue/material on the pole faces which closely matched Polydimethylsiloxane (PDMS) and silicone grease. One of the characteristics of PDMS is that at cooler temperatures it is more of a solid consistency, and at higher temperatures it becomes more viscous and tacky.
A previous Part 21 report submitted by Curiss-Wright QualTech NP (Event Notification 51611) in December 2015 provided notification of Eaton/Cutler Hammer A2DD series starters failures due to silicon based mold release that remained on the molded parts and would come between the moving (magnet) and fixed armatures. The Part 21 stated that when heated for extended period of time, the material would become sticky causing anywhere from a minor delay in opening to a frozen closed condition.* Eaton/Cutler Hammer determined that the silicone mold release was first introduced into the manufacturing facility in May 2008 and used periodically until October 2012. According to Eaton/Cutler Hammer, any starters manufactured after January 1, 2013 should be silicon mold release free.
Following the failure of the 2014 starter at Susquehanna, Eaton Corporation performed an investigation and reconfirmed that silicon mold release was banned from molding production in October 2012 and has not been used since that time. Eaton concluded that the contamination does not appear to be systemic, but rather random and intermittent and that the contamination was most likely introduced either by operators and assemblers on the manufacturing lines, or by others who disassemble and inspect the product after shipment from their plant. Susquehanna does not take the components apart during receipt for testing or visual inspection. Eaton concluded that there is no evidence that the issue is systemic and considers it a random event. Susquehanna has eval.uated the condition and has concluded that the condition could create a substantial safety hazard.
NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR NOT UNDERSTOOD? D YES (Explain above) 181 NO NRC RESIDENT x STATE(s) x DID ALL SYSTEMS FUNCTION AS REQUIRED? 181 YES D NO (Explain above) x LOCAL OTHER GOV AGENCIES MEDIA/PRESS RELEASE x
x MODE OF OPERATION:
UNTIL CORRECTED NIA IESTIMATED RESTART DATE: N/A rDDITIONAL INFO ON BACK?
0 YES 181 NO NRC FORM 361 (12-2000) PRINTED ON RECYCLED PAPER
ADDITIONAL INFORMATION PAGE2 OF2 RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific details/explanations should be covered in description)
LIQUID RELEASE I I GASEOUS RELEASE UNPLANNED RELEASE I PLANNED R'ELEASE ONGOING I I TERMINATED MONITORED I I UNMONITORED OFFSITE RELEASE I T.S. EXCEEDED RM ALARMS I I AREAS EVACUATED PERSONNEL EXPOSED OR CONTAMINATED OFFSITE PROTECTNEACTIONS RECOMMENDED *State release path in description Release Rate ICi/secl % T.S. LIMIT HOO GUIDE Total Actlvltv ICil %T.S. LIMIT HOO GUIDE Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 uCl/sec 0.01 Ci Particulate 1 uCl/sec 1 mCi Liquid (excluding tritium &
dissolved noble gases) 10 uCi/min 0.1 Ci Liquid (tritium) 0.2 Ci/min 5Ci Total Activity PLANT STACK CONDENSER/AIR EJECTOR MAIN STEAM LINE SGBLOWDOWN OTHER RAD MONITOR READINGS:
ALARM SETPOINTS:
% T.S. LIMIT (if apD/ic;able)
RCS OR SG TUBE LEAKS: CHECK O_R FILL IN APPLICABLE ITEMS: (specific details/explanations should be covered in event description)
LOCATION OF THE LEAK (e.g., SG #, valve, pipe, etc.):
LEAK RATE UNITS: gpm/gpd T.S. LIMITS SUDDEN OR LONG TERM DEVELOPMENT LEAK START DATE: TIME: OOLANT ACTIVITY PRIMARY SECONDARY UNITS:
LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL:
EVENT DESCRIPTION (Continued from front) i Ii i
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