|
---|
Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19261A1942019-09-0606 September 2019 Final Report (Log # 2019-22-00) (Event# EN 54215) - Non-Destructive Examination (Liquid Penetrant) Performance of Components by an Un-Qualified Employee 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 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 ML17199F8902017-07-11011 July 2017 Flowserve 10 CFR Part 21 Update - Stem-Wedge Separation of an Anchor/Darling Double Disc Gate Valve at LaSalle County Station, Unit 2 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 ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML15288A1992015-10-0909 October 2015 Part 21 Interim Report - Potential Defect on P/N 535-601 Moore Industries Milliamp Modules ML15259A5252015-09-16016 September 2015 Part 21 Report - Potentially Affected Coils Used in Freedom Size 1 and Size 2 Starters and Contactors ML15259A5242015-09-15015 September 2015 Westinghouse Electric Co. - Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML15077A3792015-03-13013 March 2015 Notifications of Potential Part 21 Re Weir Valves & Controls USA, Inc., - Improper Weld Used on Gate Valve Cover 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 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 ML13165A3422013-06-12012 June 2013 60-Day Interim Report Involving an Evaluation of a Design Change to Magne-Blast Circuit Breakers ML13064A0122013-02-25025 February 2013 Notification of Potential Part 21 Report Re Wedge Pin Failure of an Anchor/Darling Double-Disc Gate Valve 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 ML12283A2442012-10-0505 October 2012 Part 21 - Temperature Switch Potentially Shipped Without Set Screw ML12292A1972012-10-0505 October 2012 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0106, Rev. 0 ML12319A0122012-09-27027 September 2012 Error in Main Steam Line High Flow Calculational Methodology ML12258A3992012-09-10010 September 2012 Potential Part 21 Issue Related to Tyco Timing Relay ML12219A3042012-08-0202 August 2012 Potential Part 21 Issue Related to Tyco Timing Replay ML1219103332012-07-0707 July 2012 ATC Nuclear, Part 21 Notification Concerning Moore Process Controllers ML1219103372012-07-0202 July 2012 Update 10 CFR Part 21 Notification of Defective Moore 535 Controllers ML12177A0562012-06-21021 June 2012 Part 21 - Reliability Degradation of Resistors in Trip Units and Readout Assemblies 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 ML12094A3712012-04-0202 April 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 ML12066A1182012-03-0202 March 2012 Part 21 Report - Rosemount Pressure Transmitters with Nonzero Based Calibrations ML12058A1412012-02-23023 February 2012 Part 21 Report - Rosemount Nuclear Instruments, Inc., Pressure Transmitter 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 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 ML11284A0172011-10-0606 October 2011 10 CFR Part 21 Notification of Defective Moore 535 Controllers ML11228A0842011-08-12012 August 2011 Notification of Part 21 - Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1035001742010-12-15015 December 2010 Notification of Potential Part 21 Re 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance ML1035100312010-12-15015 December 2010 Notification of Potential Part 21 Report Concerning Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1029305052010-10-20020 October 2010 GE Hitachi Nuclear Energy - Notification of Potential Part 21 60-Day Interim Report: Crack Indications in Marathon Control Rod Blades ML1027300632010-09-27027 September 2010 Notification of Potential Part 21 Report Concerning Failure to Include Seismic Input in Reactor Control Blade Customer Guidance ML1027006142010-09-27027 September 2010 Part 21 60-Day Interim Report Notification: Failure to Include Seismic Input in Channel-Control Blade Interference Customer Guidance 2022-10-28
[Table view] Category:Letter
MONTHYEARIR 05000373/20230042024-01-24024 January 2024 County Station - Integrated Inspection Report 05000373/2023004 and 05000374/2023004 ML24024A1332024-01-24024 January 2024 Confirmation of Initial License Examination IR 05000373/20230122024-01-18018 January 2024 County Station - Biennial Problem Identification and Resolution Inspection Report 05000373/2023012 and 05000374/2023012 ML23354A2902024-01-0505 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0028 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23360A6082023-12-27027 December 2023 County Station Request for Information for NRC Commercial Grade Dedication Inspection: Inspection Report 05000373/2024010 and 05000374/2024010 ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information IR 05000373/20230032023-11-0909 November 2023 County Station Integrated Inspection Report 05000373/2023003, 05000374/2023003, and 07200070/2023001 ML23286A2602023-11-0808 November 2023 Issuance of Amendment Nos. 260 and 245 to Renewed Facility Operating Licenses Relocation of Pressure and Temperature Limit Curves to the Pressure Temperature Report IR 05000373/20234012023-11-0707 November 2023 County Station Security Baseline Inspection Report 05000373/2023401 and 05000374/2023401 RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000374/20230102023-10-11011 October 2023 NRC Inspection Report 05000374/2023010 IR 05000373/20233012023-09-15015 September 2023 Errata to NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor ML23212A9012023-08-0303 August 2023 Regulatory Audit Report to Support the Review of the Amendments to Relocation of the Pressure Temperature Limit Curves to the Pressure and Temperature Limits Report IR 05000373/20230022023-08-0101 August 2023 County Station - Integrated Inspection Report 05000373/2023002 and 05000374/2023002 ML23208A3182023-07-27027 July 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis ML23192A5272023-07-12012 July 2023 NRC Initial License Examination Report 05000373/2023301; 05000374/2023301 ML23186A2062023-07-0606 July 2023 Information Request for a NRC Post-Approval Site Inspection for License Renewal 05000374/2023010 ML23181A1502023-06-30030 June 2023 Combined Response to Request for Additional Information and Supplemental Information in Support of LAR to Relocate Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000373/20230112023-06-26026 June 2023 County Station - Quadrennial Fire Protection Team Inspection Report 05000373/2023011 and 05000374/2023011 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23167A0352023-06-16016 June 2023 Registration of Use of Cask to Store Spent Fuel ML23171A9562023-06-12012 June 2023 Post Exam Ltr RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000373/20230012023-05-10010 May 2023 County Station - Integrated Inspection Report 05000373/2023001 and 05000374/2023001 ML23123A2202023-05-0303 May 2023 Relief Request I4R-14 for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23121A1612023-05-0101 May 2023 Information Meeting (Open House) with a Question-and-Answer Session to Discuss NRC 2022 End-of-Cycle Plant Performance Assessment of LaSalle County Station, Units 1 and 2 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23107A1822023-04-18018 April 2023 Operator Licensing Examination Approval Lasalle County Station, May 2023 RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000373/20220062023-03-0101 March 2023 Annual Assessment Letter for LaSalle County Station, Units 1 and 2 (Report 05000373/2022006 and 05000374/2022006) RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station ML23024A1372023-02-0303 February 2023 Request for Withholding Information from Public Disclosure for LaSalle County Station, Unit Nos. 1 and 2 ML23031A1972023-01-31031 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information, Inspection Report Nos. 05000373/2023011 and 05000374/2023011 IR 05000373/20220042023-01-31031 January 2023 County Station - Integrated Inspection Report 05000373/2022004 and 05000374/2022004 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 2024-01-05
[Table view] |
Text
Flow Control Division Anchor/Darling Valves FLOWSERVE BW/IP Valves Edward Valves Valtek Control Products Worcester Valves November 6, 2009 US Nuclear Regulatory Commission Document Control Desk 11545 Rockville Pike Rockville, MD 20852-2746
Subject:
USNRC 10CFR Part 21 Notification Ref: Flowserve Size 3/4 Figure 848Y Disk/Disk Nut Separation LaSalle Station Exelon PowerLabs, LLC Project Number: LAS-62808 Flowserve Complaint Report 4914 Flowserve Evaluation Report No. 10 CFR 21-50 Gentlemen, This is to notify the US Nuclear Regulatory Commission, in accordance with the provisions of 10CFR-Part 21 of a deviation identified by Flowserve Corporation.
Background
On September 8, 2009, Flowserve Corporation was notified by Exelon - LaSalle Nuclear Power Station of a failure which occurred and was initially communicated via Flowserve Complaint Report
- 4914.
The Referenced Complaint Report describes an anomaly with a Size 3/4 Figure 848Y bolted bonnet valve at the LaSalle Nuclear Power Station.
The subject valve was in service at the time of disassembly. The disassembly revealed that the disk nut, which captures the valve stem in the valve main disk, had separated from the main disk.
The valve in question is a manually operated, non active valve. The safety function of this valve is to retain system pressure. This safety function was not affected by separation of the stem nut from the valve disk.
Flowserve U S Inc Raleigh Operations Toll Free: 1-800-225-6989 Flow Control Division PO Box 1961 1900 South Saunders Street Phone: 1-919-832-0525 Facsimile: 1-919-831-3369 /9 Raleigh, NC 27603 www.flowserve.com
US NRC November 6, 2009 Page 2 of 4 However, other Figure 848 valves may have different safety related functions that could be affected by this type of failure. See Discussion and Conclusion below.
Discussion Figure 1 provides an illustration of the stem/disk assembly in the Size 3/4 Figure 848 valye. The "Old Design" is typical of the valve that is the subject of this discussion. The valve stem has a collar on the very end. After the stem is inserted into the disk, the disk nut is threaded into the disk to retain the stem. A lock weld is then created to prevent the disk nut from unthreading out of the disk.
In about 1990, the design was changed to that shown as the "New Design" in Figure 1. The disk nut was eliminated, and the disk retained on the end of the valve stem using a piece of wire inserted into a groove located half in the valve stem and half in the disk.
NWr an ~mm NEW EESlID Figure 848 Figure A848 Figure 1 Stem/Disk Assemblies for Old Design and New Design Figure 848 / A848 Valves.
US NRC November 6, 2009 Page 3 of 4 For the case of the "Old Design" valve at LaSalle, once the disk nut has unthreaded out of the disk, the stem and the disk are no longer connected. The valve will then operate as a stop-check valve. The valve will open in response to normal forward flow, and close in response to normal reverse flow.
Because the disk nut is a solid piece assembled around the valve stem, the disk nut cannot fall off of the valve stem and become a loose part in the piping system.
After unthreading from the disk, the disk nut will sit on top of the disk. The valve will be able to open only partially, because the disk nut will interfere with the ability of the valve to open fully.
The amount that the valve can open will depend on the size of the valve. For the Size 3/4 valve at LaSalle, the disk would be able to open less than 1/8 of an inch. The amount that other valve sizes would be able to open is different, but all would be reduced.
In operation, the valve would function as a stop-check valve rather than a stop valve. If the handwheel is used to close the valve, the valve will remain closed. If the handwheel is used to retract the valve stem, differential pressure in the normal forward flow direction will open the valve and allow flow through the valve.
The valve handwheel will operate as though there is no problem, even though the disk is no longer connected to the valve stem.
The valve drawing does not provide a flow direction arrow, although a flow direction arrow is provided on the side of the valve body forging. If the installation was performed using the drawing as a guide, there is no guarantee that the valves were not installed backwards.
Figure 848 manually operated valves are not typically used as active safety-related devices.
Based on the above, different safety scenarios for the valve are described below:
Scenario Impact on Safety-Related function Valve has no safety-related function. None Safety-related function is to retain pressure Safety-related function is to remain closed. Safety-related function is not affected.
Safety-related function is to close against reverse flow.
Safety-related function is to pass a minimum amount of flow in the normal forward flow direction.*^,.
- ..* .. ......... *..... .. .... Safety-related function may be affected.
,dIltLy-l IdLCU IUIHILLIUI I 1. LU P=0 C1 11111111IUlll amount of flow in the normal reverse flow direction.
US NRC November 6, 2009 Page 4 of 4 Conclusion Based on the above, the Nuclear Industry needs to be notified concerning the potential defect, and encouraged to inspect the operation of their valves, especially if they have a safety-related function in the plant that may be adversely affected.
The valves affected are Size 2 and smaller Edward Figure 848 valves manufactured by Rockwell International at the Sulphur Springs, Texas, and the Raleigh, North Carolina, manufacturing facilities prior to 1991. These valves may be tagged "Rockwell", "Rockwell Edward" or "Edward".
The valves affected have the "Old Design" stem/disk assembly shown in Figure 1.
Valves with Figure Number A848 incorporate the "New Design" stem/disk connection and are not affected.
The total number of valves affected and their installed locations are not known.
Respectfully submitted, Robert D. Barry Manager, Quality Assurance Flowserve Corporation Flow Control Division 1900 S. Saunders St.
Raleigh, N.C. 27603