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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24088A1142024-02-25025 February 2024 Fairbanks Morse (Fm) Part 21 Report 23-02 Re Synchro-Start Mini-Gen Signal Generator ML22301A1742022-10-28028 October 2022 Global Nuclear Fuel Americas, LLC (GNF) - Part 21 60-Day Interim Report Notification: GNF3 Raised Water Rod (SC-22-04 Rt) ML21225A0812021-08-0404 August 2021 Lake Engineering Co., Final Report Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML20049A0742020-01-31031 January 2020 Fairbanks Morse Part 21 Re Fm Notification Report Serial Number 20-01 Fairbanks Morse ML20028D3802020-01-13013 January 2020 10CFR21 Notification for Ashcroft 2-1/2 & 3-1/2 1009, 63mm 2008, 63mm & 100mm 1008 Industrial Gauges, Weksler 3-1/2 Regal Gauges ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) ML19253A0532019-08-29029 August 2019 Azz Nuclear - Report of Potential 1O CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML19190A0442019-06-0707 June 2019 10 CFR Part 21 Reporting of Defects for Introl Positioner 890265-010 - Cw SAS Initial Report No. 10CFR21-48 ML19120A1062019-04-17017 April 2019 Interim Report of Potential 10 CFR Part 21, Eaton Size 1 and 2 A200 Series Starters/Contactors ML19121A1552019-04-15015 April 2019 Curtiss-Wright Nuclear Division, Enertech - 10 CFR Part 21 Notification for SF-1154 Hydraulic Fluid ML19101A0972019-04-0404 April 2019 Weir Valves & Controls USA, Inc. Part 21 Written Notification - Event Number: 53973 - 24 Class 150 Globe Alve for RHRSW HX Isolation MOV, E1150F068B at Detroit Edison - Fermi, Unit 2, Experienced Two Stem Failures ML19087A2512019-03-11011 March 2019 Weir Valves & Controls USA, Inc. - 10 CFR Part 21 Report: 24 Class 150 Globe Failed to Fully Open Due to the Failure of the Anti-Rotation Key ML19080A0592019-03-0808 March 2019 Interim Report of Potential 10CFR Part 21, Eaton A200 Series Starters/Contactors ML18302A2282018-10-19019 October 2018 Itt Enidine - USNRC 10CFR Part 21 Notification 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 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 ML17039A5692017-02-0303 February 2017 Final Part 21 Report on Defect, Potential for Test Induced Damage 0867F Series Main Steam Safety Relief Valves ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16321A4512016-10-21021 October 2016 Part 21 Reporting of Defects and Noncompliance ML16294A2642016-10-18018 October 2016 Part 21 Report - Defective Current to Pressure Transducers ML16278A4712016-09-22022 September 2016 Notification of 10 CFR Part 21 Condition, Masterpact Breaker Fail to Close ML16281A2702016-09-22022 September 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16243A4722016-08-25025 August 2016 Part 21 Reporting of Defects and Noncompliance ML16209A0502016-07-13013 July 2016 Part 21 - Furmanite Nuclear Grade Leak Seal Material FSC-N-1B ML16188A3742016-06-30030 June 2016 Part 21 - Inadequate Swaging and Adherence of Silicone O-Ring and Silicone PAD Soft Seat Main Disc and Pilot Disc Assemblies ML16139A8322016-05-13013 May 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16139A8332016-05-13013 May 2016 Part 21 - Initial Notification of Masterpact Breaker Fail to Close ML16139A8342016-05-10010 May 2016 Electroswitch - Transmittal of 10CFR Part 21 Reporting of Defects and Noncompliance Regarding Vendor Inspection of Electroswitch Corporation Docket No. 99900833 ML16004A0302015-12-23023 December 2015 MPR Associates, Inc. - Part 21 Report, MPR Emergency Diesel Engine Timing Module Failure, Per E.I. Hatch, Unit 2 ML16020A4762015-12-18018 December 2015 Curtiss-Wright Corp. - Notification of Part 21 Report on Eaton/Cutler Hammer A200 Series Starters (and Contactors), Per North Anna, H.B. Robinson, Diablo Canyon, and Hatch ML15357A0422015-12-18018 December 2015 Curtiss-Wright Corp. - Notification of Part 21 Report on Eaton/Cutler Hammer A200 Series Starters (and Contactors), Per North Anna, H.B. Robinson, Diablo Canyon, and Hatch ML15288A1992015-10-0909 October 2015 Part 21 Interim Report - Potential Defect on P/N 535-601 Moore Industries Milliamp Modules ML15223B2632015-08-10010 August 2015 Notification of Part 21 Interim Report - Potential Defect on P/N 535-601 Moore Industries Milliamp ML15223B2642015-08-0606 August 2015 Part 21 Report - Notification of Deviation Regarding Hk Circuit Breaker Pivot Pin ML15201A2872015-07-0808 July 2015 Crane Nuclear, Inc. - Part 21 Interim Report - Notification of Pressure Seal Valve Yoke Material Compliance ML15187A1722015-06-30030 June 2015 Interim Part 21 Report - Potential Test Induced Defect in 0867F Main Steam Safety Relief Valves ML15134A0172015-05-0101 May 2015 Part 21 Report Regarding Potential Test Induced Defect in a 0867F Main Steam Safety Relief Valves ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring ML15077A4222015-03-17017 March 2015 Curtiss Wright Flow Control Co., Interim Part 21 Report - Potential Test Induced Defect in a 0867F Main Steam Safety Relief Valves ML14365A0592014-12-23023 December 2014 Part 21 Notification - Baldor AC Motors with Potential Bearing End Cap Alignment Issues 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 ML14265A0492014-09-12012 September 2014 Amendment to Part 21 Report from Abb, Inc Re Deviation of K-Line Circuit Secondary Close Latch (Event #50371) ML14237A1212014-08-15015 August 2014 Notification of Potential Part 21 Re Notice of Deviation Regarding K-Line Circuit Breaker Secondary Close Latch ML14210A0102014-07-23023 July 2014 Part 21 - Unseating of Valve Spring on Scram Solenoid Pilot Valve ML14204A7082014-07-23023 July 2014 Enclosure 2, Description of Closure Evaluation, Non-Proprietary Information - Class I (Public) ML14204A7072014-07-23023 July 2014 Completed Evaluation of Part 21 Potentially Reportable Condition Notification: Unseating of Valve Spring on SSPV ML14112A4812014-04-15015 April 2014 Letter from James Thigpen Nuclear Nonconformance Event Number 50017 ML14101A3442014-04-10010 April 2014 Notification of Part 21 - Potential Defect in Motors Shipped to DTE Electric Co 2024-02-25
[Table view] Category:Letter
MONTHYEARML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status ML24257A1652024-09-13013 September 2024 FEMA Region 5 Fermi 2 Nuclear Power Plant Level 1 Finding September 2024 ML24256A0282024-09-12012 September 2024 2024 Hatch Requal Inspection Corporate Notification Letter NL-23-0930, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-09-11011 September 2024 Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24254A3562024-09-0909 September 2024 FEMA Level 1 Finding for Fermi 2024 Biennial Exercise NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 NL-24-0334, 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc2024-09-0303 September 2024 0 to the Updated Final Safety Analysis Report, Technical Specifications Bases Changes, Technical Requirements Manual Changes, License Renewal 10 CFR 54 .37(b) Changes, 10 CFR 50.59 Summary Report & Revised Nrc ML24240A3532024-08-27027 August 2024 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval Update IR 05000321/20240912024-08-27027 August 2024 NRC Investigation Report 2-2023-003 and NOV - NRC Inspection Report 05000321/2024091 and 05000366/2024091 IR 05000321/20240052024-08-26026 August 2024 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 and 2 - Report 05000321/2024005 and 05000366/2024005 NL-24-0313, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information2024-08-23023 August 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint Response to Request for Additional Information IR 05000341/20240052024-08-22022 August 2024 Updated Inspection Plan for Fermi Power Plant, Unit 2 (Report 05000341/2024005) IR 05000341/20240022024-08-14014 August 2024 Integrated Inspection Report 05000341/2024002 IR 05000321/20240022024-08-0808 August 2024 Edwin I Hatch Nuclear Plants, Units 1 and 2 – Integrated Inspection Report 05000321-2024002 and 05000366-2024002 NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption ML24199A2182024-07-25025 July 2024 Enrico Fermi Atomic Power Plant, Unit 1 - NRC Position on Continuation of Possession-Only License No. DPR-9 Past the Current Expiration Date (Docket No. 50-016) NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24169A4092024-07-18018 July 2024 Relief Request RR-A25, Alternative to Reactor Vessel Circumferential Shell Weld Examination ML24198A1252024-07-16016 July 2024 Edwin I Hatch Nuclear Plant Units 1 - 2 Notification of Conduct of Title 10 of the Code of Federal Regulations 50 NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 IR 05000341/20243022024-07-0909 July 2024 NRC Initial License Reexamination Report 05000341/2024302 NL-24-0240, Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link2024-07-0303 July 2024 Reactor Core Isolation Cooling (RCIC) System Inoperable Due to Mispositioned Link NL-24-0237, Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications2024-07-0303 July 2024 Incorrectly Installed Temporary Modification Results in Multiple Conditions Prohibited by Plant Technical Specifications NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 ML24173A1012024-06-14014 June 2024 Retake Exam Post-Exam Cover Letter & Comments ML24163A0532024-06-14014 June 2024 Audit Plan - Alternative Seismic Method LAR ML24155A0852024-06-11011 June 2024 Operator Licensing Reexamination Approval Letter - Fermi Power Plant, June 2024 NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities IR 05000341/20244022024-05-30030 May 2024 Security Baseline Inspection Report 05000341/2024402 ML24143A1852024-05-29029 May 2024 – Regulatory Audit in Support of LAR to Adopt TSTF-505, Rev. 2, TSTF-439, Rev. 2, and TSTF-591, Rev. 0 NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A2072024-05-20020 May 2024 Plant—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection IR 05000321/20240902024-05-15015 May 2024 NRC Inspection Report 05000321-2024090 and 05000366-2024090, Investigation Report 2-2023-003; and Apparent Violation NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0166, Manual Reactor Trip Due to Loss of Feedwater2024-05-0909 May 2024 Manual Reactor Trip Due to Loss of Feedwater NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. IR 05000341/20240102024-05-0606 May 2024 NRC Inspection Report 05000341/2024010 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 ML24052A2772024-04-30030 April 2024 Issuance of Amendment No. 229 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 IR 05000341/20240012024-04-30030 April 2024 Integrated Inspection Report 05000341/2024001 IR 05000032/20240112024-04-25025 April 2024 Notification of Edwin I. Hatch Nuclear Plant - Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 0500032/2024011 and 05000366/2024011 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0157, Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications2024-04-24024 April 2024 Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications IR 05000321/20240012024-04-22022 April 2024 Integrated Inspection Report 05000321/2024001 and 05000366/2024001 NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint 2024-09-09
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WEIR Flow Control We r Valv s & Controls USA Inc 29 Old Right Road Ipswich, MA 01938 NRC's Document Control Desk USA U.S. Nuclear Regulatory Commission T +1 978 744 5690 Washington , DC 20555-0001 F +1 978 741 3626 www.global.weir
Dear Sir or Madam ,
This notification is being submitted pursuant to the guidelinbs of 10 CFR Part 21 to report that a 24" Class 150 Globe valve for RHRSW HX Isolation MOV, E1150F068A at Detroit Edison -
Fermi 2, failed to fully open due to the failure of the anti-rotation key.
The site notified WVC USA on January 181h of this issue involving a new bonnet that was installed which included a key bushing/key assembly. The new bonnet used was from originally supplied valve assembly on WVC USA order 0010001147-10 with a quantity of one, Detroit Edison Company PO 4700732583. The key is welded on top and bottom in the key bushing keyway to hold the key in place. After a month in service , during operation the welds fa iled which caused the key to drop out or be driven out from the key bushing by friction/vibration .
Upon review of the design it was found that key and key slot fit were not dimensioned properly for a tight fit allowing a larger than recommended gap between key and keyway. This gap allowed the operational torque loads to put the welds in bending which caused the welds to fa il.
Loss of the key renders the valve inoperable to open or close.
The site has currently restored the key bushing/key assembly with new keys with proper fit and welds to ensure the key is reta ined.
Weir Valves & Controls has performed an extent condition review and has concluded that one other operating site, Georg ia Power- SNC , Hatch Unit 1 WVC USA order 0010000081-10 (55544A) , Southern Nuclear Operating Co PO SNG 10025571 has a sim ilar key/key bushing assembly. T here was a quantity of six valve assemblies shipped fo r this purchase order. The site has been contacted to evaluate the fit of the key bushing/key assem bly.
Engineering has determined that improper design clearance was the cause of fa ilure. We are performing corrective actions to ensure future re-occurrences cannot occur in design engineering.
Please fee l free to contact me with any questions or comments .
Regards ,
Allen Fisher Director of Eng ineering all en. fisher@ma il. wei r T +1 978 825 8451 M +1 252 940 9508
10 CFR PART 21 EVALUATION DOCUMENT PAGE UIEII Evaluation of Deviation or Potential Failure to Comply 1OC..FA.;i...l Ol-l'b-lCj 1 of 4 1A Identify the source of the information on the deviation or potential failure to comply:
DTE Fermi P/P 2 Contacted Weir Valves and Controls on 1/17/19 about a sheared Anti-rotation Key . Reference Customer Complaint 1234.
18 Describe the deviation or potential failure to comply that has been discovered:
Customer has reported the RHRSW HX Isolation MOV, E1150F068A, failed to open due to a failure of the anti-rotation key. Issue was noted by abnormal system response for RHRSW Pump at Start up.
1C Does the potential failure to comply represen t a violation of the Atomic Energy Act of 1954, as amended , or any applicable rule, regulation, order, or license of the NRC, including technical specification limits?
If Yes or Uncertain , a potential failure to comply exists check [gj and complete Section 1F.
If No, check D and com lete Section 1D.
1D(1) Does the deviation affect the functionality of items or services provided by Weir Valves & Controls USA?
If Yes or Uncertain, check [gj and com lete Section 1D 2 . If No, check D and com lete Section 1E.
1D(2) Does the deviation involve a basic component?
If Yes or Uncertain , check [gj and com lete Section 1D 3 . If No, check D and com lete Section 1E.
1D(3) Has the basic component been delivered to a customer?
If Yes or Uncertain , check [gj and com lete Section 1D 4 . If No, check D and com lete Section 1E.
1 D(4) Does the basic component deviate from the requirements of the customer's procurement document?
If Yes or Uncertain, check [gj and com lete Section 1G. If No, check D and com lete Section 1E.
1E No reportable deviation or potential failure to comply in accordance to 10CFR21 exists based on:
Originator (signature) Originator (print) Date Designated Responsible Officer (signature) Designated Responsible Officer (print) Date Have local Director, Quality Assurance retain this form on file for 5 years Discovery 1G I have reviewed Part 1 and determined that the deviation or potential failure to comply should be evaluated based on the basis below for reportability in accordance with 10CFR21 . (Start of 60-day clock)
D e s i g ~ l e Officer (signature)
?'!?/;er Date Within the 60-day clock started above, I will evaluate the deviation or potential failure to comply discovered in Part 1 to determine reportability in accordance with 10CFR21 .
Cognizant f echnical Engineer (signature) Date WVC_1 0CFR_EVAL 0412 16
10 CFR PART 21 EVALUATION DOCUMENT PAGE IIIEIII Evaluation of Deviation or Potential Failure to Comply 10CFR21 01-18-19.docx 2 of 4 Part 2: Technical Evaluation 2A Identification of the company supplying the basic component or activity which contains a deviation or potential failure to comply:
WVC USA supplied the basic component that failed .
28 [8J Confirm the information in Part 1. Note any discrepancies that need to be addressed:
DTE Fermi has communicated failure of anti-rotation key for EI I50F068A in which the valve failed to fully open. Pior to this event a new bonnet was installed which included the key bushing/key assembly. The new bonnet used was from originally supplied valve assembly on WVC USA order 00I0001147- 10, DTE PO 4700732583 . The key is welded on top and bottom in the key bushing keyway to hold the key in place. During operation the welds fail ed which caused the key to drop out or be driven out from the key bushing by friction/vibration.
2C Provide A) Technical Justificaiton of Unit Acceptability; or B) Proposed Technical Solution Abnormal gap between a key and bushing key slot led to a failure of the stem anti-rotating feature of the valve. This gap contributed to the premature failure of the welds and the subsequent dropping of the anti-rotation key during system operation/vibration . The key is designed to carry the full torsional force of the actuator and allow for stem displacement in the open and close direction. Due to the gap, a torsional load from the stem induced bending stress to the fillet welds . The fillet welds are only design to support, in pure shear, the weight of the key and any friction force between the stem and the key as the valve opens and closes. The aforementioned bending stress was enough to cause the fillet welds to fail which allowed the key to fall out of the bearing assembly over time. After a thorough engineering review of the original Powell design and the Weir Valves and Controls (WVC) design documentation , two issues were identified below:
- 1. It was determined, in the original Powell design , the key and key slots were to be machined with the same tolerance to create a zero clearance fit. The WVC bearing assembly drawing specifies that the keyway tolerance shall be in accordance to ANSI 817.1 which allows for maximum gap of 0.007 inches.
- 2. The original Powell design specified A 108 grade 1020 for key material. 1020 p-number is 1 wh ich is the same as the bushing (A106B). WVC design changed the key material to AISI 4140 which does not have a designated P-No. However its composition (Cr-1/2Mo) would place it somewhere close to P-3. Welding 4140 steel requires preheat. No evidence was found that the keys were properly preheated before they were welded to the bushing .
Additionally, the safety classification of the key and bushing was questioned and addressed as follows: The valve design considered Code Case N-62-7 as specified in the original customer specification. The code case provides guidance for classifying valve components not addressed in ASME Section Ill ND Code. Per N-62-7 The key is designated as a category 7 component. Per Section 4.3.3 of N-62-7 , the code case does not specify design rules, stress limits or analytical requirements for category 7 components. Therefore, the key safety significance was not altered from the original POWELL designation at the time it was reverse engineered by WVC .
[8J This issue is reportable pursuant to 10CFR21 .
0 This issue is not reportable pursuant to 10CFR21 .
0 A decision on reportability cannot be made based on the available information .
Cognizant Technical Engineer (signature) Date Review with the ORO within 5 days of completion
~~
Designated Responsible Officer (signature) 3Ji1u1 Date '
The ORO will finalize the reporting requirements and submit the reports to the NRG and any affected facilities within 30 days.
WVC_10CFR_EVAL 04 1216
10 CFR PART 21 EVALUATION DOCUMENT PAGE WEIR Evaluation of Deviation or Potential Failure to Comply 10CFR21 01 19.docx 3 of 4 Part 3: Conclusion of Reportability Evaluation 3A Basis for decision:
The decision based on supplied information is confirmed. The increased clearance between the key and key bushing and improper welding lead to the failure of the welds which prevented the valve from operating as designed.
38 Number and location of all affected components:
The extent condition review has concluded that one other operating site, Georgia Power - SNC, Hatch Unit 1 WVC USA order 0010000081 -10 (55544A), Southern Nuclear Operating Co PO SNG10025571 has a similar key/key bushing assembly. There was a quantity of six valve assemblies shipped for this purchase order. The site has been contacted to evaluate the fit of the key bushing/key assembly.
3C I have evaluated the information and technical assessment developed and 1::8] This issue is reportab le pursuant to 10CFR21 .
D This issue is not reportable pursuant to 10CFR21 .
D A decision on reportability cannot be made based on the available information .
Based on this determination, I will proceed with all proper notifications within the allowable timeframes.
Designated Responsible()fficer (signature) Datr' l/'NC_ 10CFR_EVAL 041216
CARD 18-29322 Attachment A Page 1 of 1 Attachment A Valve Diagram -1551 WE 24" Globe Valve and anti-rotation key 24'
_J To
CARD 18-29322 Attachment B Page 1 of 3 Attachment B Failed Anti-Rotation Key Location and Misaligned Keyway
CARD 18-29322 Attachment B Page 2 of 3 Attachment B Failed Anti-Rotation Key Profile
CARD 18-29322 Attachment B Page 3 of 3 Attachment B Failed Anti-Rotation Key Tack Welds
CARD 18-29322 Attachment C Page 1 of 1 Attachment C Warehouse Photo of Installed Anti Rotation Bushing and Key Abnormal Gap