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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24103A2022024-04-0909 April 2024 EN 57068 - Transco Products Inc Part 21 Initial Notification of Unverified Critical Characteristics of Darmatt KM-1 Flat Board ML21181A2202021-06-29029 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. 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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 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 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 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 2024-04-09
[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
MONTHYEARGO2-24-110, Summary of Changes and Analysis for Revision 45 of Plant Procedures Manual 13.4.1, Emergency Notification2024-11-0404 November 2024 Summary of Changes and Analysis for Revision 45 of Plant Procedures Manual 13.4.1, Emergency Notification GO2-24-109, Summary of Changes and Analysis for Revision 42 of Plant Procedures Manual 13.8.1, Emergency Dose Projection System Operations2024-11-0404 November 2024 Summary of Changes and Analysis for Revision 42 of Plant Procedures Manual 13.8.1, Emergency Dose Projection System Operations ML24290A1142024-10-17017 October 2024 CGS FPTI 2024011 GO2-24-088, Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-24024 September 2024 Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements2024-09-23023 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements ML24247A1572024-09-12012 September 2024 Withholding Determination Letter for Presentation Materials for Energy Northwest Pre-application Meeting 8-9-2024 ML24255A1012024-09-12012 September 2024 Request for Withholding Information from Public Disclosure Energy Northwest Regulatory Engagement Plan, Revision 0 GO2-24-082, Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-10010 September 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan IR 05000397/20240052024-08-22022 August 2024 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2024005) IR 07200035/20244012024-08-19019 August 2024 Security Baseline Inspection Report 07200035/2024401 IR 05000397/20244022024-08-13013 August 2024 Security Baseline Inspection Report 05000397/2024402 IR 05000397/20240022024-08-0909 August 2024 Integrated Inspection Report 05000397/2024002 GO2-24-060, Reply to a Notice of Violation, EA-21-170 and EA-23-0542024-07-30030 July 2024 Reply to a Notice of Violation, EA-21-170 and EA-23-054 GO2-24-070, Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program2024-07-29029 July 2024 Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program GO2-24-063, Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan2024-07-15015 July 2024 Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan IR 05000397/20240122024-07-10010 July 2024 – Safety Conscious Work Environment Issue of Concern Follow-up Inspection 05000397/2024012 ML24180A1482024-06-28028 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000397/2024011) and Request for Information IR 05000397/20244202024-06-27027 June 2024 – Security Baseline Inspection Report 05000397 2024420 Cover Letter GO2-24-057, Notice of Readiness for Supplemental Inspection2024-06-19019 June 2024 Notice of Readiness for Supplemental Inspection ML24099A2232024-06-12012 June 2024 Issuance of Amendment No. 275 to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling GO2-24-056, Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing2024-06-11011 June 2024 Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing ML24128A2242024-05-31031 May 2024 Issuance of Amendment No. 274 to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-13013 May 2024 2023 Annual Radiological Environmental Operating Report GO2-24-050, Annual Environmental Operating Report2024-04-30030 April 2024 Annual Environmental Operating Report IR 05000397/20240012024-04-24024 April 2024 Integrated Inspection Report 05000397/2024001 GO2-24-042, 2023 Annual Radioactive Effluent Release Report2024-04-22022 April 2024 2023 Annual Radioactive Effluent Release Report ML24089A2282024-04-15015 April 2024 – Acceptance of Requested Licensing Action License Amendment Request to Revise Columbia Generating Station Emergency Plan GO2-24-044, Voluntary Response to Regulatory Issue Summary 2024-012024-04-11011 April 2024 Voluntary Response to Regulatory Issue Summary 2024-01 ML24074A4532024-04-11011 April 2024 Request for Withholding Information from Public Disclosure IR 05000397/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000397/2024401 (Cover Letter Only) IR 05000397/20244032024-03-28028 March 2024 Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000397/2024403 GO2-24-034, Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan2024-03-20020 March 2024 Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan ML24058A0692024-03-14014 March 2024 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Emergency Plan ML24044A0492024-03-12012 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0064 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) GO2-24-041, Level of Financial Protection - Annual Reporting Requirement2024-03-12012 March 2024 Level of Financial Protection - Annual Reporting Requirement GO2-24-036, Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate2024-03-11011 March 2024 Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate GO2-24-039, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462024-03-11011 March 2024 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 ML24047A0422024-03-0707 March 2024 Issuance of Amendment No. 273 Renewed Facility Operating License and Technical Specification Clean Up IR 05000397/20230062024-02-28028 February 2024 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2023006) IR 05000397/20253012024-02-14014 February 2024 Notification of NRC Initial Operator Licensing Examination 05000397/2025301 GO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan 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 IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 05000397/LER-2024-001, Failure to Track Operability of Requirements of Transversing In-Core Probe Valves2024-01-22022 January 2024 Failure to Track Operability of Requirements of Transversing In-Core Probe Valves GO2-24-014, Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-01-15015 January 2024 Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection 2024-09-24
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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.
1
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