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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak 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) ML21225A0812021-08-0404 August 2021 Lake Engineering Co., Final Report Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML21014A2342020-12-0707 December 2020 Fourth Interim Notification Per 10 CFR Part 21 Re Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML20304A1612020-10-14014 October 2020 Lake Engineering Co., Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 Final Report Per 10 CFR Part 21 ML20097B6912020-03-20020 March 2020 Second Interim Notification Per 10 CFR Part 21: Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 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 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) 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) 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 ML17090A4002017-03-24024 March 2017 Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications ML17086A0222017-03-23023 March 2017 Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17039A5692017-02-0303 February 2017 Final Part 21 Report on Defect, Potential for Test Induced Damage 0867F Series Main Steam Safety Relief Valves ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML17026A4132017-01-11011 January 2017 Part 21 - Failure of Power Supplies to Meet Voltage Stability Specifications ML16061A0092016-02-22022 February 2016 Curtiss Wright - Part 21 Notification - Potential Defect in Okonite Tape Splices, Per James A. Fitzpatrick ML16055A1222016-02-22022 February 2016 Curtiss-Wright Corp. - Potential Defect in Okonite Tape Splices, Per James A. Fitzpatrick Nuclear Power Plant ML16039A2692016-02-0303 February 2016 Nutherm International, Inc. - Potential Issue Regarding Incorrect Industrial Irradiation Dose, Per Cooper, Oconee, Fitzpatrick, Point Beach, Brunswick, and Susquehanna ML15357A0412015-12-18018 December 2015 Nutherm International, Inc. - Potential Part 21 Report Involving RTD Transmitter, Per Fitzpatrick ML15187A1722015-06-30030 June 2015 Interim Part 21 Report - Potential Test Induced Defect in 0867F Main Steam Safety Relief Valves ML15134A0172015-05-0101 May 2015 Part 21 Report Regarding Potential Test Induced Defect in a 0867F Main Steam Safety Relief Valves ML15077A4222015-03-17017 March 2015 Curtiss Wright Flow Control Co., Interim Part 21 Report - Potential Test Induced Defect in a 0867F Main Steam Safety Relief Valves ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV W3F1-2014-0026, Notification of Potential Part 21 Report of Time-Delay Relays Spurious Actuation2014-04-11011 April 2014 Notification of Potential Part 21 Report of Time-Delay Relays Spurious Actuation ML14079A0282014-03-13013 March 2014 Part 21 - Allen Bradley Type 700RTC Relay Spuriously De-Energizing ML13238A2532013-08-21021 August 2013 Notification of Potential Part 21 Report - Foxboro Power Supply Potential Failures Due to Defective the Wraps and Holders ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13127A0122013-05-0303 May 2013 Notification of Potential Interim Part 21 Report of Defect in a Relief Valve Bellows ML13093A1532013-04-0202 April 2013 Part 21 Report - Foxboro Power Supply Potential Failures Due to Defective Tie Wraps and Holders ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML13042A0962013-02-0808 February 2013 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Error in Main Steam Line High Flow Calculational Methodology 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 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 ML12319A0112012-09-27027 September 2012 Part-21 Report - Faulty Master Trip Units, Slave Units, and Resistance Temperature Detectors ML12177A0562012-06-21021 June 2012 Part 21 - Reliability Degradation of Resistors in Trip Units and Readout Assemblies ML12163A1302012-06-0606 June 2012 Part 21 Report - Failure of CRD Collet Retainer Tube/Outer Tube Weld ML12158A4472012-06-0606 June 2012 Part 21 60-Day Interim Report Notification - Closufailure of CRD Collet Retainer Tube/Outer Tube Weld ML12094A3712012-04-0202 April 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12040A2832012-02-0707 February 2012 Notification of Potential Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance 2024-04-12
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0611612011 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Paze I Power Reactor Event# 46964 Site: FITZPATRICK Notification Date / Time: 06/16/2011 12:14 (EDT)
Unit: 1 Region: 1 State: NY EvenrtDate/Time: 06/15/2011 14:00 (EDT)
Reactor Type: [1] GE-4 Last Modification: 06/16/2011 Containment Type: MARK I NRC Notified by: EUGENE DORMAN Notifications: JUDY JOUSTRA R1DO HQ Ops Officer: PETE SNYDER Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 UNSPECIFIED PARAGRAPH Unit Scram Code RX Crit lnit Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 100 Power Operation 100 Power Operation ROSEMOUNT MODEL 710 TRIP UNITS WOULD NOT TURN ON DURING TESTING "On June 15. 2011, the site vice president was notified that the 10 CFR 21 evaluation of.Rosemount Model 710 Trip Units supplied under purchase order 10174727 determined that the reporting criteria of 10 CFR 21.21 (d)(1) are met.
"During pre-installation testing it was found that 3 of 4 Rosemount Model 710 Trip Units would not turn on. The units were returned to Rosemount for failure analysis and it was determined that a resistor in the start-up circuit for the trip unit was failed. This prevented the trip unit from starting. Based on engineering analysis some of the applications for the trip unit require it to energize to perform the associated safety functions. Therefore, the identified failure mechanism could have represented a substantial safety hazard if the components had been installed, and the condition is reportable.
"The condition had no actual safety consequences as the deficiency was identified during pre-installation testing and if installed without pre-installation testing the system could not have passed post maintenance testing. The three failed units were returned to Rosemount. This notification is made pursuant to 10 CFR 21(d)(ii)(3)(i)."
The licensee notified the NRC Resident Inspector.
@6/16/2011 12:14 3153436480 JAF SITE VP PAGE 02/02 PAGE 1 OF 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSiON (12-2000) REACTOR PLANT OPERATIONS CENTER EVENT NOTIFICATION WORKSHEET EN #
NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-100 or 800-532-3469*, BACKUPS - (let] 301-951-0550 or B00-442-3e54",
.2ndi 301-415-0550 and [3rdl 301-415-0553 "Licensees who maintain their own ETS are provided these telephone numbers.
NOTIRCAllON TIME FACIUITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #
. ,ao* ,I James A- Fitzpatrick NPP 1 Eugene Dorman (315) 349-6810 1.Zota rGNTTIME ERWr UATE POUEhMIODE *:*RE POVWERMODE AFTER 1400 06/15/2011 Mode 1 /100% Mode 1 / 100%
EVENT CLASSIFICATIONS I-Hr. Non-Emergency 10 CFR 60.72(b1) .. (v)(A) Safe SIO Capability ANNk GENGRp.. EMERGENCY GEN(AAEC Devian AT Aj (0)3) RW-R COPONRY ANW ST 5IAREAEMERGENCY Wr/AAEC 4-Hr. Non-Ememency 10 CFR 60.72 b)(2) -- (v)(C) Controterf Rad Release AINC ALERT A-E/AAE - 0) TS Required SO A,.-U (v)(D) Ac6ident Mitigation AM LNUSUAL EVENT LNUIAAEC (iv)(,) ECCS Diftmme 10 RCS ACCS (d) Offalte MediCal AMED 50,72 NON-EBsERGENCy (see nan columns) (Iv)(B) RPS Actuation (scramn) PW'5 tat) Loss Conlm/AsmtiResp xw PHYSICAL SECURITY (73.71) tM (xi) O*,ste Notincalon AE 60-Day Optional 10 CFR 60.73(a)(1)
MATERIALEXPOSURE 277? 8-Hr. Non-Emerency 10 CFR 50.72(b)(3) Irivaflkspecf*fied st ,n Actuation RTNE55FoR Duty 0THLPISPEýCE REaDrEMT terr J(i(CO Dgraded Consoo AmEG Other Unspecified Requirement (identify)
AMt (sselastcolumn) (B) unanst-"dCondition Q AutA, v/' 10 (IF2, ,,Jd)Lii)( £ roe
. INFORMATION ONLY -p 1(ivfA) Specifid Syater Actuation A ....
DESCRIPTION Include: Systems effecWte,ectuations and their initiating signal., causes, effect of event on plant. actions taken or plasneo. etc. (Confltnue ornback)
On June 15, 2011, the site Vice President was notified that the 10 CFR 21 evlauation of Rosemount Model 710 Trip Units supplied under purchase order 10174727 determined that the reporting criteria of 10 CFR 21.21(d)(1) are met,.
During pre-installation testing ftwas found that 3 of 4 Rosemount Model 710 Trip units would not turn on:- The units were returned t t0 Rosemount for failure analysis and it was determined that a resistor in the start-up circuit for the trip unitwas failed. This prevented the up Lin k I i i~SLEI ung.., aedb onq enginee rirng analysissom associated safety functions. Therefore, the identified failure olw 11*.10alpplicatilons forthe tri p unlit require t to energize to perform the mechanism could have represented a substantial safety hazard IFthe components had been installed, and the condition is reportable.
The condition had no actual safety consequences as the deficiency was identified during pria-installation testing and if Installed without pre-installation testing the system could not have passed post maintenance testing. The three failed units were returned to Rosemount.
This notification is made pursuant to 10 CFR 21(d)(ii)(3)(i).
NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR 0 YES (ExpJain above NO NRC RESIDENT /
STATE(S)
LOCAL i NOT UNDERSTOOD?
DID ALL SYSTEMS Vo FUNCTION AS REQUIRED? [ YES NO (Explain above)
OTHER GOV AGENCIES V MODE OF OPERATION ESTIMATED ADlmoNAI INFO ON BPO(
MEDIA/PRESS RELEASE / UNTIL CORRECTED RESTART DATE: D E$ NO NRC FORM 381 (12-2000)