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Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARJAFP-21-0029, Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2021-04-29029 April 2021 Revision to Commitment Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML20296A2762020-10-0606 October 2020 Lake Engineering Co. - Third Interim Notification Per 10 CFR Part 21 - Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML19263A6662019-09-0909 September 2019 Lake Engineering Co. - Third Interim Notification Per 10 CFR Part 21: Degraded Snubber SF1154 Hydraulic Fluid Batch No. ZJS1518 ML19029A1552018-12-27027 December 2018 10 CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0123, Rev. 1 ML18353A4282018-11-30030 November 2018 Engine Systems, Inc., 10CFR21-0123, Rev. 0, for a 10CFR21 Reportable Condition on Emd Fuel and Soakback Pumps ML18263A2812018-09-20020 September 2018 (Waterford 3) - Part 21 Report of Westinghouse 7300 Circuit Card Increased Failure Rate ML17325B0222017-11-17017 November 2017 Fisher Controls International LLC Information Notice (FIN) 2017-05 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 ML15134A0172015-05-0101 May 2015 Part 21 Report Regarding Potential Test Induced Defect in a 0867F Main Steam Safety Relief Valves ML15089A4362015-03-21021 March 2015 Part-21 Report - Valve Seat Leakage Defect W3F1-2014-0069, Part 21 Report of Time-Delay Relay Failure2014-11-12012 November 2014 Part 21 Report of Time-Delay Relay Failure 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 W3F1-2014-0042, Part 21 Report of Pneumatic Valve Actuator Reverse Action2014-07-0909 July 2014 Part 21 Report of Pneumatic Valve Actuator Reverse Action 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 ML14107A1612014-04-0909 April 2014 Qualtech Np Response to 10CFR Part 21 Notification on Allen Bradley Timing Relays, Event # 49911, Docket No. 99901414 ML14079A0282014-03-13013 March 2014 Part 21 - Allen Bradley Type 700RTC Relay Spuriously De-Energizing 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 ML12319A0112012-09-27027 September 2012 Part-21 Report - Faulty Master Trip Units, Slave Units, and Resistance Temperature Detectors 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 ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12097A3162012-03-0202 March 2012 Part 21 Report - Rosemont Pressure Tranmitters Out of Tolerance Condition ML1127000672011-09-26026 September 2011 GE-Hitachi Part 21 Reportable Condition Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1025202192010-09-0303 September 2010 Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance 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 ML0923900432009-08-25025 August 2009 Notification of Potential Part 21 Report Due to Radiation Monitor Defect ML0907611882009-03-11011 March 2009 Part 21 Notification - Defective Hk and K-Line Circuit Breaker Tension Springs ML0723304752007-08-14014 August 2007 Rosemount 1154 Pressure Transmitter Calibration Problem ML0228102902002-09-30030 September 2002 Main Steam Line Valve Out-of-Service Final Report 2021-04-29
[Table view] Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML23065A2002023-03-0303 March 2023 EN 56252 Update - Flow Serve - Final Notification of Potential Part 21 on Peerless 56 Frame DC Motors ML23030A6642023-01-27027 January 2023 Flowserve, Part 21 Second Interim Notification Report Re Peerless 56 Frame DC Motors ML22342B1402022-12-0202 December 2022 56252-EN 56252 - Flowserve - Limitorque - Interim Report Potential Part 21 on Peerless 56 Frame DC Motors 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 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 ML20097B6912020-03-20020 March 2020 Second Interim Notification Per 10 CFR Part 21: Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 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 ML18241A0292018-08-23023 August 2018 Hex Inverter Chip on Westinghouse 7300 Process Analog Control System Circuit Cards W3F1-2018-0040, Interim Report of a Deviation or Failure to Comply2018-07-0505 July 2018 Interim Report of a Deviation or Failure to Comply ML18081A1192018-03-15015 March 2018 Rosemount Nuclear Instruments, Inc., Submittal of Notification Under 10 CFR Part 21 for Certain Model 1154 and Model 1154 Serles H Pressure Transmitters and 01154-0153-0002 Amplifier Circuit Card Assemblies 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) ML17325B0222017-11-17017 November 2017 Fisher Controls International LLC Information Notice (FIN) 2017-05 ML17324A9792017-11-17017 November 2017 Part 21 Report Re Fisher Type 461 Valve Plug Machining 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 ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16188A3762016-06-21021 June 2016 Part 21 Interim Evaluation of Deviation - Contractor Failure 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 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 ML15303A0042015-10-23023 October 2015 Part 21 Report Regarding Westinghouse Type KIR-60 Current Transformer, Per Waterford, Unit 3 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 ML15103A4852015-04-0707 April 2015 Itt Engineered Valves - 2nd Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M I Diaphragms, Customer Testing ML15089A4362015-03-21021 March 2015 Part-21 Report - Valve Seat Leakage Defect 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 W3F1-2014-0069, Part 21 Report of Time-Delay Relay Failure2014-11-12012 November 2014 Part 21 Report of Time-Delay Relay Failure 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 ML14261A1502014-09-17017 September 2014 Interim Report to the NRC of 10 CFR 21 Event 50285, Reported by Itt 07/18/14 Concerning M1 Diaphragms, Customer Testing ML14265A0492014-09-12012 September 2014 Amendment to Part 21 Report from Abb, Inc Re Deviation of K-Line Circuit Secondary Close Latch (Event #50371) ML14237A1212014-08-15015 August 2014 Notification of Potential Part 21 Re Notice of Deviation Regarding K-Line Circuit Breaker Secondary Close Latch 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) 2023-03-03
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Text
073113120114 Pll !T p 03/13/2014 I~US'. Nucehar Rt'pulaonrv
-.-------- J-. Commission flnerations.Centler Event Rpnnrt
-r----- Pagop 1 Part 21 (PAR) Event# 49911 Rep Org: WATERFORD STEAM ELECTRIC STATION Notification Date I Time: 03/13/2014 14:46 (EDT)
Supplier: QUALTECH NP Event Date I Time: 03/12/2014 16:00 (CDT)
Last Modification: 03/13/2014 Region: 4 Docket #:
City: KILONA Agreement State: Yes County: License #:
State: LA NRC Notified by: JOHN JARRELL Notifications: MARC FERDAS R1DO HQ Ops Officer: DONG HWA PARK KATHLEEN O'DONOHUE R2DO Emergency Class: NON EMERGENCY DAVE PASSEHL R3DO 10 CFR Section: THOMAS FARNHOLTZ R4DO 21.21(d)(3)(i) DEFECTS AND NONCOMPLIANCE PART 21 GROUP EMAIL PART 21 - ALLEN BRADLEY TYPE 700RTC RELAY SPURIOUSLY DE-ENERGIZING "This is a non-emergency notification from Waterford 3 required under 10 CFR PART 21 concerning an apparent deviation from dedicated manufacturing specifications.
"On 10/17/2013, it was determined that there have been multiple inadvertent actuations of Engineered Safety Features Actuation Signal (ESFAS) equipment over the previous seven months. These equipment inadvertent actuations are occurring due to Allen Bradley type 700RTC relays spuriously de-energizing. The failure mode causes the relays to intermittently de-energize causing the associated equipment to perform its ESFAS function, not adversely impacting steady state plant operations.
"The failed relays have been sent to the qualifying vendor and two other failure analysis laboratories for testing.
The results were reviewed by Waterford 3 engineers and although the failure mode could not be repeated in the laboratory, the laboratories identified less than adequate solder joints on the relay control circuit and a failed capacitor. The cause of the failed capacitor was identified as less than adequate installation practices during manufacturing. Engineering has determined that effects of these deviations, combined with installation in an application near the qualifying vendor's maximum specified environmental conditions, relevant to elevated voltage and ambient temperatures, has resulted in accelerated aging effects on the sub-components of the relays. The failures have been observed on relays that have been in-service greater than three years.
"Entergy concluded that for the applications for which the failure mode has been observed, and for other applications where these relays have been installed for more than 3 years, the failures did not result in a substantial safety hazard. However, on 3/12/2014, Entergy completed an evaluation concluding that, had this relay type been installed in other safety related normally energized applications for greater than 3 years, it could have resulted in a substantial safety hazard. Compensatory measures to preclude the malfunction of these relays, until
03/13/2014 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page 2 long-term corrective actions are completed, have been implemented. As an interim measure the installed time for these relays is limited to 3 years or less, The Waterford 3 Site VP was informed the same day, 3/12/2014.
"Waterford 3 has determined that the only other Entergy nuclear facility utilizing these Allen Bradley relay types, possibly in a safety related application, is at James A. Fitzpatrick, to which this condition has been communicated."
The licensee has notified the NRC Resident Inspector.
03/11/2014 19:54 5647396678 VP: OFFICE PAGE 61 PAGE 1 OF 2 NRC FORM 381 REACTOR PLANT U.s. NUCLEAR REGULATORY COMMISSION (12-2000)
OPERATIONS CENTER EVENT NOTIFICATION WORKSHEET EN #
NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-5100 or 800-532-346r, BACKUPS - [1st] 301-g51-0550 or 800-449-3694*.
r2ndi 301-415-0550 and [3rdl 301-415-0553 *Licensees who maintain their own ETS ara provided these telephone numbers, NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #
Waterford 3 John Jarrell 504-739-6685 EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER 1600 CDT 03/12/2014 100% / MODE 1 100% / MODE 1 EVENT CLASSIFICATIONS I-Hr. Non-Emergency 10 CFR S0.72(h)(1) (v)(A)_ Safe S/I Capability AINA GENERAL1EMERGENCY GEN/AAEC ED TS DeMelatoii AOEV U lv(B) RHR Cpab~llfty AINE LU SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) v C) Cornrol of Rad Releas. AJNC F
.i ALERT, UNUSUAL EVENT ALEIAAEC UNU/AEC ED (1) TS ReqWred So/
Ilfv)(A)ECCS DlachO7ge to RCS ASHU ACCOS (v)(O)
(xII)
Accident Mitgatin Ofmslte Medical AIND AMED 50,72 NON-EMERGENCY (see next columnns) [] (ivXB) RPS Atuti.on (scram) ARPS (xii) L.e Comn/'At/Re.p ACOM
[ PHYSICAL SECURITY (73.71) DODD 0i (xi) Offltle Notificbaon APRE 50-Day Optional I1 CFR 50.73(a)(1)
Ul MATERIAL/EXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50,72(b)(3) U Invalid Specified System Actuation AINV Q FITNESS FOR DUTY HFIT U (OiXA) Degraded CondItion ADEG Other Unspecified Requirement (Identffy)
OTHER UNSPECIFIED REOMT. (see last olurnn) Ii (jl)(B) Unanalyzed Condition AUNA Z 10 CFR 21.21(dX3Xi) Defect NONR INFORMATION ONLY NNF 1 (ivXA) Specified Semrn Actuation AESF UQ NONR DESCRIPTION This is a non-emergency notification from Waterford 3 required under 10 CFR PART 21 concerning an apparent deviation from dedicated manufacturing specifications.
On 10117/2013, it was determined that there have been multiple inadvertent actuations of Engineered Safety Features Actuation Signal (ESFAS) equipment over the previous seven months, These equipment inadvertent actuations are occurring due to Allen Bradley type 700RTC relays spuriously de-energizing. The failure mode causes the relays to intermittently de-energize causing the associated equipment to perform its ESFAS function, not adversely impacting steady state plant operations.
The failed relays have been sent to the qualifying vendor and two other failure analysis laboratories for testing. The results were reviewed by Waterford 3 engineers and although the failure mode could not be repeated in the laboratory, the laboratories identified less than adequate solder joints on the relay control circuit and a failed capacitor. The cause of the failed Capacitor was identified as less than adequate installation practices during manufacturing. Engineering has determined that effects of these deviations, combined with installation in an application near the qualifying vendors maximum specified environmental conditions, relevant to elevated voltage and ambient temperatures, has resulted in accelerated aging effects on the sub-components of the relays. The failures have been observed on relays that have been in-service greater than three years.
Entergy concluded that for the applications for which the failure mode has been observed, and for other applications where these relays have been installed for more than 3 years, the failures did not result in a substantial safety hazard. However, on 3/12/2014, Entergy completed an evaluation concluding that, had this relay type been installed in other safety related normally energized applications for greater than 3 years, it could have resulted in a substantial safety hazard. Compensatory measures to preclude the maffunction of these relays, until long-term corrective actions are completed, have been implemented. As an interim measure the installed time for these relays is limited to 3 years or less. The Waterford 3 Site VP was informed the same day, 3/12/2014.
Waterford 3 has determined that the only other Entergy nuclear facility utilizing these Allen Bradley relay types, possibly in a safety related application, is at James A. Fitzpatrick, to which this condition has been communicated.
NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR El YES (Explain above) [ NO NRC RESIDENT UEl U NOT UNDERSTOOD? YES STAT ; " U D ALL SYSTEMS ES NO (Explain above)
LOC L FUNCTION AS REQUIRED?
VP: OFFICE PAGE 02 03/11/2014 19:54 5847396676 ADDITIONAL INFORMATION PAGE 2 OF 2 I DAflifl nemm-AL FECAOi flfl- C UV flD FIL INIii AnAlira 3
- -ýanfrwnuwc. PTUWu An.a .W~~A..# J-L ý I-5 ~~pm
[] LIQUID RELEASE fIGASEOUS RELEASE L] UNPLANNED RELEASE [] PLANNED RELEASE j] ONGOING [3 TERMINATED
[7 MONITORED []UNMONITORED [] OFFSITE RELEASE [] T. S. EXCEEDED [] RM ALARMS [3 AREAS EVACUATED
[3PERSONNEL EXPOSED OR CONTAMINATED [] OFFSITE PROTECTIVE ACTIONS RECOMMENDED -slate release path indewepdfon Release Rate (Ci/sec) % T. S, UMIT HOD GUIDE Total Activity CI) % T. S. LIMIT HOO GUIDE Noble Gas 0.1 Cilsec 1000 C0 Iodine 10 uClc _ _ 0.01 Ci Particulate I uCi/sec I mCi Liquid (excluding &M num and dissolved noble gases) 10 uCimin 0.I Cl Liquid (trifium) 0.2 Ci/min ,, S Ci Total Activity , ,_._J PLANT STACK CONDENSERIAIR EJECTOR MAIN STEAM UNE SG SLOWDOWN OTHER RAO MONITOR READINGS ALARM SETPOINTS
% T. S. UMIT (7f avlcahle)
RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (spec/fi de&aiWL/expwanatons should be covered in event descpilpion)
LOCATION OF THE LEAK fe,g.. So 4t valve, pi, etc.)
LEAK RATE UNITS: gpm/gpd T. S. LIMITS SUDDEN OR LONG-TERM DEVELOPMENT LEAK START DATE TIME COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS:
LIST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Contned from front)
03/11/2014 19:54 5047396678 VP: OFFICE PAGE 63 OTHER SOV AGENCIES El 0Z 0] MODE OF OPERATION ESTIMATED ADDITIONAL INFO ON BACK MEDINPFRESS RELEASE ]UNTIL CORRECTED: N/A RESTART DATE. N/ IES ONO NRC FORM 361 (1 2-2000)