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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) 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 ML14072A3282014-03-13013 March 2014 Part 21 60-Day Interim Report Notification Re Unseating of Valve Spring on SSPV 2022-10-28
[Table view] Category:Letter
MONTHYEARIR 05000341/20230042024-02-0505 February 2024 Integrated Inspection Report 05000341/2023004 IR 05000321/20230042024-01-31031 January 2024 Integrated Inspection Report 05000321/2023004 and 05000366/2023004 NL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. ML24012A0652024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000321/20233012024-01-17017 January 2024 NRC Operator License Examination Report 05000321/2023301 and 05000366/2023301 ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23310A1492023-12-0808 December 2023 Issuance of Amendment No. 227 Regarding Revision of Technical Specification 3.8.1, AC Sources - Operating, Emergency Diesel Generator Voltage and Frequency Surveillance Requirements ML23341A1852023-12-0808 December 2023 Acknowledgement of Response to NRC Inspection Report 05000341/2023402 and Disputed Non-Cited Violation IR 05000341/20230102023-12-0808 December 2023 Nbsp;Biennial Problem Identification and Resolution Inspection Report 05000341/2023010 NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems IR 05000016/20230012023-12-0101 December 2023 NRC Inspection Report No. 050-00016/2023-001 (Drss) - Enrico Fermi Atomic Power Plant, Unit 1 ML23334A1902023-12-0101 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000341/2024010 ML23335A0062023-12-0101 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000341/2024002 NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation IR 05000321/20234022023-11-29029 November 2023 Security Baseline Inspection Report 05000321/2023402, 05000366/2023402, and 07200036/2023401 NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal IR 05000321/20230112023-11-17017 November 2023 Biennial Problem Identification and Resolution Inspection Report 050003212023011 and 050003662023011 ML23324A4472023-11-14014 November 2023 302 Exam Approval Letter IR 05000341/20230032023-11-0707 November 2023 Integrated Inspection Report 05000341/2023003 and 07200071/2023001 IR 05000321/20230032023-11-0202 November 2023 Integrated Inspection Report 05000321/2023003, and 05000366/2023003 ML23297A0512023-10-30030 October 2023 Issuance of Amendment No. 226 Regarding Revision of Technical Specifications 3.8.1, AC Sources - Operating (Exigent Circumstances) IR 05000321/20234032023-10-26026 October 2023 Cyber Security Inspection Report 05000321/2023403 and 05000366/2023403 ML23311A3482023-10-20020 October 2023 DTE Electric Company (DTE) - Submittal of the Renewed Fermi 3 Michigan Department of Environmental, Great Lakes, and Energy (EGLE) National Pollutant Discharge Elimination System (NPDES) Permit No. MI0058892 IR 05000321/20234012023-10-17017 October 2023 Security Baseline Inspection Report 05000321 2023401 and 05000366 2023401 ML23272A1552023-10-10010 October 2023 Letter to Licensee and Federal Register Notification of Amendment to Renewed Facility Operating License and Proposed No Significant Hazards Consideration Determination (Exigent Circumstances) (EPID L-2023-LLA-0134) (Letter) ML23283A0222023-10-0909 October 2023 Follow Up to Fermi Unit 2 Inservice Testing (IST) Program for the Fourth 10-Year Inspection Interval ML23276B4542023-10-0505 October 2023 Cyber Security Inspection Report 05000341/2023402 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23243A8852023-09-18018 September 2023 Issuance of Amendment No. 225 Regarding Revision of Technical Specifications 3.7.2, Emergency Equipment Cooling Water, Emergency Equipment Service Water and System and Ultimate Heat Sink (Exigent Circumstances) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report ML23248A2242023-09-0707 September 2023 Regulatory Audit in Support of Review of License Amendment Request for a Risk-Informed Approach for Addressing the Effects of Debris on ECCS Strainer Performance ML23223A2242023-08-29029 August 2023 Individual Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing (Exigent Circumstances) IR 05000321/20230052023-08-27027 August 2023 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 & 2 - Report 05000321/2023005 and 05000366/2023005 ML23237B4332023-08-25025 August 2023 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and RFI IR 05000341/20230052023-08-24024 August 2023 Updated Inspection Plan for Fermi Power Plant, Unit 2 (Report 05000341/2023005) ML23229A0122023-08-17017 August 2023 Issuance of Amendment No. 224 to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 (Emergency Circumstances) IR 05000341/20233012023-08-16016 August 2023 NRC Initial License Examination Report 05000341/2023301 ML23227A2212023-08-15015 August 2023 Emergency Application to Revise Technical Specifications to Adopt TSTF 568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 IR 05000321/20230022023-08-0808 August 2023 Integrated Inspection Report 07200036/2023001, 05000321/2023002, and 05000366/2023002 ML23219A1792023-08-0707 August 2023 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Fermi Power Plant, Unit 2 ML23216A1872023-08-0404 August 2023 Submittal of Relief Request RR-A25 for Extended License Period NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis IR 05000341/20230022023-08-0404 August 2023 Integrated Inspection Report 05000341/2023002 2024-02-05
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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