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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML21181A2202021-06-29029 June 2021 Part 21 Written Notification - P21-03302021 Rev. 2 - Failures of Size 1 and 2 Freedom Series Full Voltage Reversing Starters ML21126A1722021-04-29029 April 2021 Paragon Energy Solutions Failures of Size 1 and 2 Freedom Series Full Voltage Reversing Starters 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 ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) GO2-19-129, Part 21 Notification Re Failure Analysis Concluded That Overvoltage Conditions Caused Overheating and the Subsequent Failures of Starter Coils Contained in Spectrum Technologies Buckets2019-09-0303 September 2019 Part 21 Notification Re Failure Analysis Concluded That Overvoltage Conditions Caused Overheating and the Subsequent Failures of Starter Coils Contained in Spectrum Technologies Buckets 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 GO2-17-156, Transmittal of 10 CFR 21.21 (d)(4) Notification, GE-Hitachi Relays HMA124A22017-09-0606 September 2017 Transmittal of 10 CFR 21.21 (d)(4) Notification, GE-Hitachi Relays HMA124A2 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 ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 GO2-17-086, 10 CFR Part 21 Notification Regarding Size 1 Freedom Series Starters2017-04-13013 April 2017 10 CFR Part 21 Notification Regarding Size 1 Freedom Series Starters ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17081A4542017-03-17017 March 2017 Part 21 Notification - Evaluation of a Deviation - Starter Contactor Failure 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 ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16251A0982016-09-0202 September 2016 Part 21 - Potential Failure of Battery System Connections ML16188A3762016-06-21021 June 2016 Part 21 Interim Evaluation of Deviation - Contractor Failure ML15211A4962015-07-24024 July 2015 Part 21 - Actuator Shaft Did Not Meet Dimensional Requirements ML14337A0942014-11-24024 November 2014 Notification of Potential Part 21 - Lack of Proper Power Supply Indication 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 ML14169A2582014-06-16016 June 2014 Part 21 - Scram Solenoid Pilot Valve Not Exhausting Properly ML14139A2592014-05-0808 May 2014 10 CFR Part 21 Report Notification, NUS710DU Trip Units ML14134A0792014-05-0808 May 2014 Part 21 - Potential Defect in NUS-710DU Trip Unit to Produce a Valid Trip Output Signal ML14072A3282014-03-13013 March 2014 Part 21 60-Day Interim Report Notification Re Unseating of Valve Spring on SSPV ML14072A3262014-03-13013 March 2014 Enclosure 2: Description of Evaluation ML14079A0262014-03-11011 March 2014 Notification of Part 21 Re Scram Solenoid Pilot Valve Not Exhausting Properly ML14034A1902014-01-27027 January 2014 Part 21 - Possible Defect in a High Efficiency Particulate Air Filter 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 ML13142A3292013-05-0606 May 2013 Notification of Potential Part 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10CFR21-0109, Rev. 0 ML13127A0142013-05-0303 May 2013 Part 21 Report - Fuel Injectors Failed Pressure Test 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 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 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 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 ML1035100312010-12-15015 December 2010 Notification of Potential Part 21 Report Concerning 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 2021-06-29
[Table view] Category:Facsimile
MONTHYEARML14079A0262014-03-11011 March 2014 Notification of Part 21 Re Scram Solenoid Pilot Valve Not Exhausting Properly 2014-03-11
[Table view] Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
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03/1112014 U.S. Nuclear Resulatorv Commission Overadons Center Event Revort plaire N 204
.... .S.NulaReuarvCmiio Oneatins-entr E entRn --am -a Part 21 (PAR) Event# 49895 Rep Org: ASCO VALVE INCORPORATED Notification Date I Time: 03/11/2014 13:00 (EDT)
Supplier: ASCO VALVE INCORPORATED Event Date / Time: 03/11/2014 (EDT)
Last Modification: 03/11/2014 Region: 1 Docket #:
City: AIKEN Agreement State: Yes County: License #:
State: SC NRC Notified by: BOB ARNONE Notifications: THOMAS FARNHOLTZ R4DO HQ Ops Officer: CHARLES TEAL PART 21 GROUP EMAIL Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 (a)(2) INTERIM EVAL OF DEVIATION PART 21 - SCRAM SOLENOID PILOT VALVE NOT EXHAUSTING PROPERLY The following was excerpted from a fax received from ASCO Valve, Inc.:
"Problem Description "GE Hitachi Nuclear Energy (GEH) customer Energy Northwest reported that an ASCO scram solenoid pilot valve (SSPV) Catalog number HVL266000010J 115/60, GE-H part number 107E6022P014, serial number A272718-054, CRD-SPV-1 18/1043 did not exhaust properly. The valve had been installed in Energy Northwest's Columbia facility for approximately 7 months and had been cycled 60-70 times. Energy Northwest's internal investigation revealed the pilot head assembly spring was not in the groove of the associated core.
"Conclusion "Various tests were performed to rule out possible manufacturing non-conformances in the spring or core. The successful completion of these tests has established that when the spring is properly installed on the core, the spring will not come off in service. We have not yet identified any other conditions that could cause the spring to come off the core, except for improper assembly.
"This configuration of spring and core design was used on the original 090405 scram valve. There has not been any design change to this core assembly since its inception in 1959. This spring/core assembly makes up the bulk of ASCO core solenoid offering. It is used across all of ASCO valve ranges in the Commercial, Nuclear, Military, and Petrochemical markets. ASCO has supplied over 10 million valves to these markets over the entire product offering. This Includes over 50,000 Nuclear Qualified Valves. With the exception of the 1994 and 2012 events, a review of ASCO return records found no other cases of this condition where a spring disengaged from the core.
O3*/,f1/2044 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Page 2 "Since ASCO does not have adequate knowledge of the actual installations and operating conditions of these valves, it was not able to be determined if this could create a 'Substantial safety hazard' as defined in 10 CFR Part
- 21. This information is intended to provide interim investigation results.
"If you have any questions, you can contact Bob Arnone at 803-641-9395."
Mar. 11, 2014 1:03PM No. 0140 P. 1 EMERSON. As=a Industrial Automation numaTlSu.
Facsimile ASCO Valve, Inc.
1561 Columbia Highway Aiken, SC 29801 T (803) 641-9353 F (803) 641-0290 www. asconum alGs. CorM To: NRC Documents Control Desk No. of Pages (includingcover sheet) 6 Company: NRC Fax Number: 301-816-5151 Date March 11, 2014 From: Bob Arnone Phone: 803-641-9395 Comments: To whom it may conern:
Attached is Interim Letter to NRC Document Control Desk and one referenced exhibit. If there are any questions and/or the transmission is not legible, please call 803-641-9395.
Sincerely, Bob Arnone Sr. Technical Service Engineer
Mar. 11, 2014 1:03PM No. 0140 P. 2 EMERSON.
4 Industrial Automation ASCO Valve, Inc.
1561 Columbia Highway Aikan, SC 29801 USA T (803) 641-9200 F (803) 641-9290 www.asconumaticsicom March 11th, 2014 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
Subject:
Interim Report on HVL266000010J Valve Reference A - ASCO letter to GE Hitachi Nuclear Energy dated Nov. 9, 2012.
Problem
Description:
GE Hitachi Nuclear Energy (GEH) customer Energy Northwest reported that an ASCO scram solenoid pilot valve (SSPV) Catalog number HVL266000010J 115160, GE-H part number 107E6022P014, serial number A272718-054, CRD-SPV-118/1043 did not exhaust properly. The valve had been installed in Energy Northwest's Columbia facility for approximately 7 months and had been cycled 60-70 times. Energy Northwest's internal investigation revealed the pilot head assembly spring was not In the groove of the associated core.
Cause Analysis:
Energy Northwest dis-assembled the valve for inspection and determined that the core spring was disengaged from the core assembly. In addition, the diaphragm assemblies of the valve were inspected and Energy Northwest determined them to conform to specifications. Inspection also found small amounts of foreign material in the valve internals. This foreign material (found as brass debris) is typically generated during dis-assembly and would not affect the function of the valve.
ASCO received the loosely assembled valve from Energy Northwest on RMA 58315. The core, spring, and Solenoid Base Sub-Assembly were inspected by ASCO Quality Assurance. All components were verified to be in compliance with specifications. A spring cycle test was performed and confirmed that a properly installed spring will not detach from the core assembly.
This test was performed with the solenoid both vertical and horizontal. An additional 42 valves from the same order were subsequently inspected during this investigation and all were properly assembled.
ASCO had investigated a similar occurrence in October, 2012 on RMA 53914 (GElH CAR #
58997). That investigation concluded that this was an isolated case of an improperly assembled spring. Corrective action was implemented by ASCO on November 9, 2012, involving an additional inspection step to verify the spring was installed properly on all valves that use the conical spring/core assembly. Ref. A. Prior to October 2012, the only other similar occurrence was in 1994 at Commonwealth Edison's Dresden facility. At that time ASCO determined it was an Isolated case and implemented an additional quality inspection step of the core and spring assembly to verify proper installation of the spring.
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Mar. 11. 2014 1:03PM No. 0140 P. 3 Interim Action:
Prior to 2010, these valves were manufactured in ASCO's Florham Park facility, and it was general practice to have Quality inspect the spring/core assembly. Such inspection would, have discovered the misassembly of the spdng .in the Energy Northwest valve, In 2010, manufacturing of these valves was transferred to the Aiken facility. The spring/core assembles of valves manufactured at the Aiken facility were not inspected until the additional inspection step described above was implemented starting November 9, 2012.
From March 29, 2010 through November 9, 2012, 449 SSPV's were manufactured at the Aiken facility. 45 valves were recently returned to ASCO on RMA's 58315, 58449 and 58472. 44 valves were Inspected and detertmined to have properly installed springs. The remaining one is the subject of this report. Two valves were reworked on RMA 53914 of Nov, 2012 and three returned on RMA 54714 were scrapped. Thus, 401 of the 449 original SSPV's remain to be inspected.
Pending the completion of the investigation described below, ASCO believes that the only way to verify that a spring is properly Installed on a core is visual inspection of the spring/core assembly. ASCO does not recommend Inspection to be performed in the field as dis-assembly of the top retaining nut may cause a piece of the nylon thread locker to fall down into the core/plugnut area and cause improper operation and noise. ASCO believes it is unlikely that other SSPV valves are affected. In order to further support the investigation, it is requested that valves removed from installation or inventory be returned for further evaluation at the earliest convenience.
GEH ASCO Valve Year Shipment Complete Catalog Number P0 Number 05 No. S/N Date 2010 2011 2012 HV266000010J115/60JA 437028521 213561 A171767. Apr 09 2010 50 HV266000010J115/60JA 437028521 213579 A321861 Mar 29 2010 50 HV266000010J1 15/60EA 437046605 477985 A726654 Mar 11 20i1 3 Jan- Feb HV26600001WJ115/60EA 437058358 651136 Ai18888 2012 158' Jul - Sep HV26600001ORI15/6OKA 437051484 551580 A793691 2011 108 H.V266000010J115/60KA. 437067889 802504 A272718 Sep 28 2012 80**
Included 2 valves that were reworked and 3 that were scrapped.
- Of the 80 valves shipped on GEH P0 437067889, 45 have been returned on RMA's 58315, 58449 and 58472. A complete list of serial numbers for affected valves still in the field will be supplied to GEH for transmittal to their customers.
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Mar. 11. 2014 1:03PM No. 0140 P. 4 Continuing ASCO Investigation:
ASCO is performing additional tests to attempt to determine the maximum number of cycles an improperly installed spring can handle in the particular application of the SSPV operating conditions. In bench testing, ASCO confirmed that an improperly installed spring can in some cases outlast the qualified cycle life of the valve when rapidly cycled. This condition Is now being tested in the actual operating conditions of the operating plant. This testing can take up to 3 months (end of June 2014) to complete. ASOQ believes it is unlikely that other 8SPV valves are affected. In order to further support the investigation, it is requested that valves removed from installation or inventory be returned for further evaluation at the earliest convenience.
Closure and Conclusion; Various tests were performed to rule out possible manufacturing non-conformances in the spring or core. The successful completion of these tests has established that when the spring is properly installed on the core, the spring will not come off in service. We have not yet Identified any other conditions that could cause the spring to come off the core, except for Improper assembly.
This configuration of spring and core design was used on the original 090405 scram valve.
There has not been any design change to this core assembly since its inception in 1959. This spring/core assembly makes up the bulk of ASCO core solenold offering. It Is used across all of ASCO valve ranges in the Commercial, Nuclear, Military, and Petrochemical markets. ASCO has supplied over 10 million valves to these markets over the entire product offering. This Includes over 50,000 Nuclear Qualified Valves. With the exception of the 1994 and 2012 events, a review of ASOC return records found no other cases of this condition where a spring disengaged from the core.
Since ASCO does not have adequate knowledge of the actual Installations and operating conditions of these valves, it was not able to be determined if this could create a "substantial safety hazard" as defined in 10 CFR Part 21. This information is intended to provide Interim investigation results.
If you have any questions, you can contact Bob Arnone at 803-641-9395.
Sincerely, Lams Gacall Vice President Quality Americas Asco Valve Inc.
3 of 3
Mar. 11. 2014 1:03PM No. 0140 P. 5 EMERSON.
Industri6al Automation ASCO Valve, Inc.
1561 Columbia Highway Aiken, SC 29801 USA T (803) 641-9200 F (803) 641-9290 www.asconumatics.com REFERENCE A November 9, 2012 GE-Hitachi Nuclear Energy 3901 Castle Hayne Road Wilmington, NC 28401 Attn: Darion Jeralds Ref: RMA 53914
Dear Darion,
Two of valve catalog number HV266000010J 115/60, were returned assembled in series from Plant Fermi I1. The reported problem is the valves were not shifting to the de-energized position when required. Serial numbers are A113888-025 (Valve 117, inbound), and Al13888-068 (Valve 118, outbound).
During dis-assembly of valve Al 13888-068 (#118) it was discovered that the spring was not installed on the core. ASCO performed tests showing that this was the cause of the valve not exhausting properly in its as-received condition. The -025 (#117) valve passed all ASCO tests and operated acceptably in it's as- received condition.
An inspection step has been implemented to verify that the spring is installed properly. This has been done on all nuclear valves that use the conical spring/core assembly.
As there was no tamper sealant on the valve, ASCO cannot determine if the valve has been disassembled prior to its return. ASCO will be including tamper proof sealant on the pressure boundary joints of all Scram Solenoid Pilot Valves on all future shipments.
ASCO has not identified any process, material, assembler, design or equipment changes or non-conformances related to the core and spring which would affect its assembly. Based on experience ASCO believes this is an isolated case of one valve because:
- 1. This configuration of spring & core design was used on the original 090405 scram valve.
- 2. There has not been any design change to this core assembly since its inception in 1959
- 3. This spring/core design makes up the bulk of our core solenoid offering. It is used across all of our valve ranges in the Commercial, Nuclear, Military, and Petrochemical markets. ASCO has supplied over 10 million valves to these markets over the entire product offering.
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Mar. 11. 2014 1:03PM No, 0140 P. 6
- 4. In all cases we have not identified a single case of this condition where the spring came free of the core.
- 5. ASCO identified over 50,000 Nuclear Valves made using this same configuration.
There have been no incidences of this anomaly recorded.
Based on the above analysis ASCO maintains that this is an isolated case. ASCO believes the above is a complete decision basis for isolation and to treat this as a singular anomaly, At the Request of GE-H ASCO inspected the diaphragms of both valves. The material is in good condition, no foreign material is in the bleed holes of all 4 diaphragms.
Due to variations in core &spring tolerances ASCO does not feel any further testing attempting to replicate a partially installed spring would yield any reliable conclusions and ASCO would not be able to support any conclusions gained from additional tests.
The core and spring from valves 117 & 118 where both checked, which showed that the spring and core meet all of their required dimensions. A spring cycle test was then performed to determine if a properly installed spring would come off of cores 117 & 118 with the springs installed on the cores properly. The successful completion of this test proves that when the spring is properly installed on the core that the spring will not come off in service.
The spring/core assembly issue and the reported leakage from the tubes (see CAR #58596) are not linked.
ASCO does not have adequate knowledge of the actual installations and operating conditions of these valves to determine whether this condition could create a "substantial safety hazard" as defined in 10 CFR Part 21. This information is intended to provide investigation results and to answer the questions sent via email. This has been verified in accordance with 10CFR part 50 Appendix B.
Sincerely, Bob Arnone Technical Service Engineer 2