|
---|
Category:Deficiency Correspondence (per 10CFR50.55e and Part 21)
MONTHYEARML24175A0042024-06-23023 June 2024 Interim Report of a Deviation or Failure to Comply Associated with a Valve in the Unit 3 High Pressure Coolant Injection System ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump ML22075A2192021-11-29029 November 2021 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0133, Rev. 0 - Swing Check Valve, P/N ESl50359 ML20279A5772020-11-23023 November 2020 U.S. Nuclear Regulatory Commission'S Analysis of Public Service Enterprise Group Nuclear, LLC Decommissioning Plans Update for Salem Generating Station, Hope Creek Generating Station and Peach Bottom Independent Sfsis 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 ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19158A1302019-05-31031 May 2019 Curtiss-Wright Nuclear Division - Notification Report for Potential Part 21 Update ML19078A0872019-03-0808 March 2019 Curtiss-Wright - Interim Notification Report for Potential Part 21 Update ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML19008A0432019-01-0404 January 2019 Third Interim Notification Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11KLVS146 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 ML18332A1222018-11-15015 November 2018 Curtiss-Wright - Interim Notification Report for Potential Part 21 Update ML18302A2282018-10-19019 October 2018 Itt Enidine - USNRC 10CFR Part 21 Notification ML18159A0392018-06-0606 June 2018 National Technical Systems (Nts) - Potential Part 21 on Dedicated Items Not Available for Pmi Testing (NUPIC) ML18075A3552018-03-0606 March 2018 10 CFR Part 21 Notification of Defect on Crane Nuclear Figure Number 83 1/2 Spl 10x8x10 and 6x4x6 Bolted Bonnet Gate Valve ML17355A1392017-12-0505 December 2017 Potentially Degraded Snubber SF1154 Hydraulic Fluid Batch 14ELVS145 Final Report Per 10 CFR Part 21 ML17206A0392017-07-13013 July 2017 Part 21 - Hex Cap Screws Produced with Pre-existing Cracks ML17114A0692017-04-19019 April 2017 Part 21 Report - Control Rod Drive Mechanisms Contaminated with Chlorides ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML16328A3152016-11-22022 November 2016 Part 21 - Incorrect Capacitor Used on Circuit Boards ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML16252A2742016-08-29029 August 2016 Azz/Nli - Part 21 Report - Potential Allen Bradley Timing Relay ML15259A5212015-09-10010 September 2015 Part 21 Report - Potential Failure of Electromatic Relief Valve Cutout Switches ML15243A1742015-08-25025 August 2015 Part 21 Furmanite Nuclear Grade Leak Seal Material FSC-N-1B ML15223B2662015-08-0707 August 2015 Part 21 Report - Crane Nuclear Pressure Seal Valve with Retaining Rings ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15161A2302015-06-0404 June 2015 Part 21 Report Regarding Potential Failure of a Time Relay at Quad Cities ML15134A0162015-05-0101 May 2015 Part 21 Report Regarding Potentially Unqualified Component in Certain Allen Bradley Timing Relays ML14365A0592014-12-23023 December 2014 Part 21 Notification - Baldor AC Motors with Potential Bearing End Cap Alignment Issues ML14309A5292014-10-31031 October 2014 Closure of 10 CFR Part 21 Interim Report - Engine Systems, Inc., Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14259A3892014-09-0808 September 2014 Part 21 - Failure to Meet Specified Irradiation During Testing of Coated Test Panels ML14318A1962014-09-0505 September 2014 CFR Part 21 Interim Report - Engine Systems, Inc. - Emergency Diesel Generator Heat Exchanger CEY564L-HEX ML14216A3772014-07-30030 July 2014 Part 21 Report - Incorrect Industrial Irradiator Dose 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 ML14189A4172014-07-0707 July 2014 Closure of 10 CFR Part 21 Interim Report - Limitorque Valve Motor - Motor Operator of SMB-0 Valve Actuator ML14192A0382014-07-0303 July 2014 Part 21 Report Incorrect Industrial Irradiator ML14112A4812014-04-15015 April 2014 Letter from James Thigpen Nuclear Nonconformance Event Number 50017 ML14105A0182014-04-11011 April 2014 Part 21 - Model 1154HP Transmitters with Integral 1159 Remote Diaphragm Seals May Exhibit Degraded Functional Reliability ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14069A4672014-02-26026 February 2014 Part 21 Report Involving a Potential Manufacturing Defect in Replacement Masterpact Cradles ML13260A0772013-09-12012 September 2013 10 CFR Part 21 Interim Report - General Electric (GE) Hitachi Nuclear Energy - Sbm Type Manual Switch ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13094A1772013-03-18018 March 2013 Notice to the U.S. Nuclear Regulatory Commission of a Possible Deviation or Defect in Nuclear Qualified High Efficiency Particulate Air Filters Manufactured by Aaf ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML13008A3212013-01-0404 January 2013 Anti-Rotation Pin Failure in Anchor Darling (Flowserve) Double Disc Gate Valve 2024-06-23
[Table view] Category:Part 21 Correspondence
MONTHYEARML19008A0432019-01-0404 January 2019 Third Interim Notification Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 11KLVS146 RA-17-059, Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2017-08-29029 August 2017 Commitments for Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML15243A1742015-08-25025 August 2015 Part 21 Furmanite Nuclear Grade Leak Seal Material FSC-N-1B ML15223B2662015-08-0707 August 2015 Part 21 Report - Crane Nuclear Pressure Seal Valve with Retaining Rings ML15223B2642015-08-0606 August 2015 Part 21 Report - Notification of Deviation Regarding Hk Circuit Breaker Pivot Pin ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14079A0272014-03-13013 March 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML13246A0872013-08-23023 August 2013 Nuclear Nonconformance Event Number 49302 - 10CFR21 Notification ML13044A0752013-02-0808 February 2013 Part 21 - Completed Evaluation for Potential Error in Main Steam Line High Flow Calculational Methodology ML1024605372010-09-0202 September 2010 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1000700732009-11-19019 November 2009 USNRC 10CFR Part 21 Notification - Flowserve Figure 848 Disk/Disk Nut Separation ML0902103762008-12-30030 December 2008 December 2008 OL Exam (SRO Exam with Answers) ML0714302622007-05-17017 May 2007 10 CFR Part 21 Report Concerning 3 and 4 Borg Warner Check Valves, Amendment of Information Previously Supplied ML0608600852006-03-21021 March 2006 Rosemount Nuclear Instruments, Inc., Notification Under 10 CFR Part 21 for Model 1153 and Model 1154 Pressure Transmitters ML0529103892005-10-13013 October 2005 Part 21 Communication: Testing to ANSI Standards Complete on Circuit Breaker Replacement Primary Bushings ML0501102232005-01-0707 January 2005 Non-Emergency Event Report, Overstress Condition on Single Failure Proof Crane Trolleys ML0428002672004-09-29029 September 2004 Submittal of Part 21 Final Report: Non-conservative SLMCPR ML0335301272003-12-16016 December 2003 Part 21 Report on Potential Concern Regarding Specific Lot of Fluorocarbon Rubber Inserts ML0320604292003-07-21021 July 2003 Notification of Possible Defect Associated with Thermo Westronics Model 2100C Series Recorders ML0215601132002-05-10010 May 2002 Letter from W. G. Hampton Subject: 10CFR21 Notification - Potential Defect Involving Fan Assemblies Use in Forced Air Cooled Uninterruptible Power Supply Systems 2019-01-04
[Table view] |
Text
0311312014 Pap* I 031/04U.S. Nuclear Reuulatorv Commission Onerations Center Event Renort Pa-i I Part 21 (PAR) Event # 49908 Rep Org: GE HITACHI NUCLEAR ENERGY Notification Date I Time: 03/13/2014 13:05 (EDT)
Supplier: ASCO VALVE, INC. Event Date / Time: 01/16/2014 (EDT)
.Last Modification: 03/13/2014 Region: 1 Docket #:
City: WILMINGTON Agreement State: Yes County: License #:
State: NC NRC Notified by: LISA SCHICHLEIN 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 (a)(2) INTERIM EVAL OF DEVIATION PART 21 GROUP EMAIL PART 21 - UNSEATING OF VALVE SPRING ON SCRAM SOLENOID PILOT VALVE "This concerns an evaluation being performed by GE Hitachi Nuclear Energy (GEH) regarding a malfunction of a Scram Solenoid Pilot Valve (SSPV), which has been observed to impair control rod scram performance. As stated herein, GEH has not concluded that this is a reportable condition in accordance with the requirements of 10CFR 21.21(d). The SSPV manufacturer (ASCO Valve, Inc.) has not yet concluded its own investigation under IOCFR 21, and the results of that investigation are needed as input for the GEH evaluation. The manufacturer has issued an Interim Report, which provides confidence that this condition is limited to a very small portion of the suspect population.
"A malfunction of a Scram Solenoid Pilot Valve was attributed to the disengagement of the valve spring from the valve plunger. The effect of the malfunction is to degrade scram performance of an affected control rod. The safety significance of this condition cannot be determined at this time, but several mitigating and compensatory functions have been identified."
This evaluation affects Fermi 2, Columbia, Dresden 2-3, Oyster Creek, Peach Bottom 2-3, Quad Cities 1-2, and Browns Ferry 1-3.
- HITACHI GE Hitachi Nuclear Energy Proprietary Notice Dale E. Porter This letter transmits proprietary information GE-Hitachi Nuclear Energy Americas LLC in accordance with 10CFR2.390. Upon Safety Evaluation Program Manager removal of Enclosure 1, the balance of this 3901 Castle Hayne Rd.,
letter may be considered non-proprietary. Wilmington, NC 28401 USA T 910 819-4491 Dale.Porter@GE.Com March 13, 2014 MFN 14-010 RO U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Subject Part 21 60-Day Interim Report Notification:
Unseating of Valve Spring on SSPV This letter provides information concerning an evaluation being performed by GE Hitachi Nuclear Energy (GEH) regarding a malfunction of a Scram Solenoid Pilot Valve (SSPV), which has been observed to impair control rod scram performance. As stated herein, GEH has not concluded that this is a reportable condition in accordance with the requirements of 10CFR 21.21(d). The SSPV manufacturer (ASCO Valve, Inc.) has not yet concluded its own investigation under 10CFR 21, and the results of that investigation are needed as input for the GEH evaluation. The manufacturer has issued an Interim Report, which provides confidence that this condition is limited to a very small portion of the suspect population.
The information required for this GEH 60-Day Interim Report Notification per §21.21(a)(2) is provided in Attachment 2. The commitment for follow-on actions is provided in Attachment 2, item (vii).
If you have any questions, please call me at (910) 819-4491.
Sincerely, Dale E. Porter Safety Evaluation Program Manager GE-Hitachi Nuclear Energy Americas LLC
MFN 14-010 RO Page 2 of 2 Attachments:
- 1. US Plants Potentially Affected
- 2. 60-Day Interim Report Notification Information per §21.21(a)(2)
Enclosures:
- 1. Description of Evaluation, GEH Proprietary Information - Class II (Internal)
- 2. Description of Evaluation, Non-Proprietary Information - Class I (Public)
- 3. Affidavit cc: J. Golla, USNRC S. S. Philpott, USNRC S. J. Pannier, USNRC
- 0. Tabatabai-Yazdi, USNRC D. C. Crawford, GEH J. F. Harrison, GEH J. G. Head, GEH J. Burke, GEH P. L. Campbell, GEH Washington PRC File PLM Spec 000N5377 RO Document Components:
001 MFN 14-010 RO Cover Letter.pdf 002 MFN 14-010 RO Enclosure 1 Proprietary.pdf 003 MFN 14-010 RO Enclosure 2 Non-Proprietary.pdf 004 MFN 14-010 RO Enclosure 3 Affidavit.pdf
MFN 14-010 RO Page 1 of 1 Attachment 1 US Plants Potentially Affected US BWR Plants and Associated Facilities Plant Constellation Energy Nine Mile Point 1-2 x Detroit Edison Co. Fermi 2 x Energy Northwest Columbia Entergy Grand Gulf Entergy River Bend Entergy FitzPatrick Entergy Pilgrim Entergy Vermont Yankee Exelon Clinton x Exelon Dresden 2-3 Exelon LaSalle 1-2 Exelon Limerick 1-2 x Exelon Oyster Creek x Exelon Peach Bottom 2-3 x Exelon Quad Cities 1-2 FirstEnergy Nuclear Operating Co. Perry 1 Florida Power &Light Duane Arnold Nebraska Public Power District Cooper PPL Susquehanna LLC Susquehanna 1-2 Progress Energy Brunswick 1-2 PSEG Services Corp. Hope Creek Southern Nuclear Operating Co. Hatch 1 - 2 x Tennessee Valley Authority Browns Ferry 1-3 Xcel Energy Monticello North East Utilities Millstone
MFN 14-010 RO Page 1 of 2 Attachment 2 Day Interim Report Notification Information per §21.21(a)(2)
(i) Name and address of the individual or individuals informing the Commission.
Dale E. Porter GE Hitachi Nuclear Energy Safety Evaluation Program Manager 3901 Castle Hayne Road, Wilmington, NC 28401 (ii) Identification of the facility, the activity, or the basic component supplied for such facility which fails to comply or contains a defect.
See Attachment 1 for a list of potentially affected U.S. plants (iii) Identification of the firm constructing the facility or supplying the basic component which fails to comply or contains a defect.
GE Hitachi Nuclear Energy (ASCO Valve, Inc., manufacturer)
(iv) 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.
A malfunction of a Scram Solenoid Pilot Valve was attributed to the disengagement of the valve spring from the valve plunger. The effect of the malfunction is to degrade scram performance of an affected control rod. The safety significance of this condition cannot be determined at this time, but several mitigating and compensatory functions have been identified.
Mv)The date on which the information of such defect or failure to comply was obtained.
A Potential Reportable Condition Evaluation in accordance with 10 CFR Part 21 was initiated on January 16, 2014.
lvi) 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.
SSPVs from a production population identified by the manufacturer are currently considered suspect (though considered to have low likelihood of being affected). Those SSPVs were shipped by GEH to the following plant sites in the quantities indicated in the following table.
MFN 14-010 RO Page 2 of 2 Attachment 2 Day Interim Report Notification Information per §21.21(a)(2)
Plant Quantity Browns Ferry 3 Columbia Generating Station 20 Dresden 2 Enrico Fermi 2 162 Oyster Creek 88 Peach Bottom 8 Quad Cities 6 Non-U.S. Plant 110 (vii) 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.
After the 2012 occurrence of this condition, the manufacturer completed a corrective action to implement an in-process inspection to ensure that SSPV valve springs are properly engaged with the plungers. This action was completed in November 2012.
(viii) 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.
GEH suggests that plant staff with valves from the affected populated assist the manufacturer's investigation as practical.
(ix) In the case of an early site permit, the entities to whom an early site permit was transferred.
This is not an early site permit concern.