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Category:Deficiency Report (per 10CFR50.55e and Part 21)
MONTHYEARML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24008A0692024-01-0404 January 2024 Part 21 Report No. 10CFR21-0137, Rev. 0 for Reportable Notification for an Emo Cylinder Liner with Bore Deficiency, P/N 9318833 (Component of Power Assembly P/N 40124897), S/N 20M0938 ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 ML24002A7112023-12-28028 December 2023 Interim Part 21 Report of a Deviation or Failure to Comply - Lube Oil Scavenging and Fuel Oil Engine Driven Pump ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23094A1242023-03-31031 March 2023 EN 56387 Update - Paragon Energy Solutions Final Notification of Defect of Automatic Transfer Switch ML23094A1252023-03-31031 March 2023 Talen Part 21 Final Notification P21-03032023-FN R0 Re Defect Identified in Automatic Transfer Switch ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 ML23060A0412023-03-0101 March 2023 Part 21 Interim Report of a Deviation or Failure to Comply Associated with a Limitorque Actuator ML23025A2532023-01-25025 January 2023 Part 21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML23024A0292023-01-24024 January 2023 Part 21 Interim Report of a Deviation or Failure to Comply Associated with a Limitorque Actuator ML21225A0812021-08-0404 August 2021 Lake Engineering Co., Final Report Per 10 CFR Part 21 Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML21014A2342020-12-0707 December 2020 Fourth Interim Notification Per 10 CFR Part 21 Re Degraded Snubber SF1154 Hydraulic Fluid Batch No. 17BLVS293 ML20073G4572020-03-0909 March 2020 Carrier Corporation - Final Report Notification of Defect Pursuant to 10 CFR Part 21 for 17FA999-1200-107 Oil Pump ML20049A0752020-02-11011 February 2020 C&D Technologies, Inc. -10 CFR Part 21 Evaluation Regarding Container Failure in KCR-07 Batteries ML20042E2522020-01-31031 January 2020 EN 54485 Target Rock Redacted Update to Part 21 Report on Defect of Modification of Valve Component and Main Disc Lift Misadjustment ML20029D1612020-01-21021 January 2020 10 CFR Part 21 Report, Notification of a Defect Modification of a Valve Component and Main Disc Lift Misadjustment ML20021A0452020-01-0303 January 2020 Lake Engineering Co. - Interim Notification Per 10 CFR Part 21, Degraded Snubber SF1154 Hydraulic Fluid Batch No. 16DLVS852 ML19347A4262019-12-10010 December 2019 General Atomics - Reportable Occurrence Under 10CFR21: Reported Failure in Analog High Range Radiation Monitor (RP-2C) 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 ML19106A1062019-04-12012 April 2019 Ametek Solidstate Controls - Notification of Potential Defect - 10 CFR Part 21 ML18087A0022018-03-21021 March 2018 Crane Nuclear, Inc. - Final Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem 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 ML17223A1982017-07-21021 July 2017 Part 21 Notification - Eaton/Cutler Hammer A200 Series Starter ML17206A0402017-07-14014 July 2017 Part 21 - Defective Safety Related Valves PLA-7613, Interim Report of a Deviation, Units 1 & 2 - (PLA-7613)2017-06-0909 June 2017 Interim Report of a Deviation, Units 1 & 2 - (PLA-7613) ML17179A3782017-06-0707 June 2017 TE Connectivity - Part 21 Transfer of Information TE-023 ML17114A0702017-04-13013 April 2017 Part 21 Notification - Identified Fisher 546S Electro-Pneumatic Transducers Standard Mounting Brackets Failed Seismic Testing Standards ML17081A4532017-03-20020 March 2017 Part 21 - Plastic Jar Dedication Sampling ML17026A4142017-01-20020 January 2017 C&D Technologies, Inc. - Part 21 - Plastic Jar Dedication Sampling ML16313A0622016-10-18018 October 2016 C&D Technologies, Inc. - 10 CFR Part 21 Evaluation Regarding Terminal Welding Failure in 3DCU-9 Batteries ML16321A4502016-08-31031 August 2016 Part 21 Notification - Flowserve Swing Check Valves 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 ML16154A2062016-05-18018 May 2016 Part 21 Report - Defect in a Signal Converter Transformer ML16039A2692016-02-0303 February 2016 Nutherm International, Inc. - Potential Issue Regarding Incorrect Industrial Irradiation Dose, Per Cooper, Oconee, Fitzpatrick, Point Beach, Brunswick, and Susquehanna ML15254A2772015-09-0808 September 2015 Part 21 Notification Re Westinghouse Corporation Deviation from Contract Service ML15223B2642015-08-0606 August 2015 Part 21 Report - Notification of Deviation Regarding Hk Circuit Breaker Pivot Pin ML15103A2442015-04-0606 April 2015 Part 21 Report - Deviation of Hk Circuit Breaker Close Latch Spring ML15099A0422015-04-0202 April 2015 Notification of Part 21 Report - Potentially Defective Pressure & Temperature Switches ML15099A0432015-04-0202 April 2015 Amendment to Event Number 50299, 10 CFR Part 21 Notification, Potentially Defective Pressure & Temperature Switches ML15049A4582015-02-0606 February 2015 Thermo Gamma-Metrics, LLC - Part 21 Report Regarding Shutdown Margin Monitor Environmental Qualification Noncompliance ML15034A5662015-01-23023 January 2015 Notification of Potential Part 21 for Event #50703 ML15030A0332015-01-20020 January 2015 Letter from James Thigpen Notification of Potential Part 21 Nuclear Nonconformance Event Number 50703 ML15022A6502015-01-20020 January 2015 Letter from Steven R. Eisenberg USNRC 10CFR Part 21 Notification ML14337A0942014-11-24024 November 2014 Notification of Potential Part 21 - Lack of Proper Power Supply Indication ML14329A0632014-11-19019 November 2014 Notification of Potential Part 21 Re Lack of Proper Power Supply Indication 2024-01-04
[Table view] Category:Letter
MONTHYEARIR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 ML24032A0202024-01-31031 January 2024 NPDES Biocide/Corrosion Treatment Plan Annual Report, Cy 2023 ML23319A2452024-01-29029 January 2024 Issuance of Amendment Nos. 366 and 360; 164 and 71 Regarding the Adoption of TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues ML24018A0142024-01-17017 January 2024 Engine Systems, Inc., Report No. 10CFR21-0137, Rev. 1, 56913-EN 56913 CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24011A3182024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), October 2023 ML24011A3192024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), November 2023 ML24011A3202024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), December 2023 IR 05000327/20234422024-01-11011 January 2024 95001 Supplemental Inspection Report 05000327/2023442 and 05000328/2023442 and Follow-Up Assessment Letter ML24011A3162024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), August 2023 ML24011A3172024-01-11011 January 2024 Submittal of Discharge Monitoring Report (Dmr), September 2023 ML24010A2132024-01-10010 January 2024 CFR 21.21 Final Report Regarding Siemens Medium Voltage Circuit Breakers ML24018A0952024-01-0404 January 2024 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance Report No. 10CFR21-0137, Rev. 0 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval ML24004A0332024-01-0303 January 2024 Interim Report of a Deviation or Failure to Comply Crompton Instruments Type 077 Ammeter ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) CNL-23-068, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)2023-12-18018 December 2023 Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08) ML23346A1222023-12-12012 December 2023 Annual Non-Radiological Environmental Operating Report - 2023 IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual IR 05000327/20234202023-11-28028 November 2023 Security Baseline Inspection Report 05000327/2023420 and 05000328/2023420 CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23324A4362023-11-0909 November 2023 Exam Corporate Notification Letter Aka 210-day Letter ML23307A0822023-11-0808 November 2023 Request for Additional Information August 4, 2022, Exemption Request for Deviating from the Conditions of Certificate of Compliance No. 1032, Amendment No. 3, Related to Sequoyah Nuclear Plant Independent Spent Fuel Storage Installation PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 IR 05000327/20230032023-11-0303 November 2023 Integrated Inspection Report 05000327/2023003 and 05000328/2023003 ML23306A1592023-11-0202 November 2023 Enforcement Action EA-22-129 Inspection Readiness Notification PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23292A0792023-10-19019 October 2023 Tennessee Valley Authority - Emergency Plan Implementing Procedure Revision, Includes EPIP-5, Revision 58, General Emergency IR 05000327/20230112023-10-16016 October 2023 Triennial Fire Protection Inspection Report 05000327/2023011 and 05000328/2023011 ML23285A0882023-10-12012 October 2023 Submittal of Sequoyah Nuclear Plant, Units 1 and 2, Submittal of Updated Final Safety Analysis Report Amendment 31 ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23284A4252023-10-11011 October 2023 10 CFR 50.59 and 10 CFR 72.48 Changes, Tests, and Experiments Summary Report; Commitment Summary Report; and Update to the Fire Protection Report ML23283A2792023-10-10010 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information ML23277A0462023-10-0404 October 2023 Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Specification Bases ML23275A0272023-09-29029 September 2023 Submittal of Discharge Monitoring Report (DMR) Quality Assurance Study 43 Final Report 2023 ML23271A1662023-09-28028 September 2023 Registration of Spent Fuel Storage Cask Pursuant to 10 CFR 72.212(b)(2) CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-059, Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-2023-09-20020 September 2023 Supplement to Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Application to Revise Technical Specifications to Adopt TSTF-567-A, Revision 1, Add Containment Sump TS to Address GSI-191 Issues (SQN-TS-23-03 IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23257A0062023-09-14014 September 2023 Enforcement Action EA-22-129 Inspection Postponement Request 2024-02-07
[Table view] |
Text
MAR.21.2018 11:43AM NO. 403 P. 2 TELEPHONE (630) ~\J-,.>'VV FA:X(630)226-4646 www.crancn1.1clell{.tlO.tn NUCLEAR CRANE NUCLEAR,. INC. 860 REMINGTON BOULEVARD BOLINGBROOK, IL. 60440 Date: 3/21/2018 Attn: Document Control D'esk U.S. Nuclear Regulatory Commission Washington, D.C. 20555~001 Subject; Final Report for 10 CBR Part 21 Investigation Report Notification ofXOMOX Plug Valve High Torsional Stress in Stem This letter provides final notification of Crane Nuclear 1 s (CNl) investigation into the subject Part 21 notification previously provided to the Nuclear Regulatory Commission on 07/11/17 (i) Name and address ofthe individual 01- individuals informing the Commission.
- Joyce Hantman Director, Safety and Quality Burt Anderson Site Leader Samson Kay Engineering Manager Crane Nuclear 860 Remington Blvd Bolingbrook, IL 60440 (ii) Identification of the basic component supplied for such facility or such activity within the United Stares which may fail to comply or contatns a potential defect The plug valve designs provided for XOMOX model figure nlllnbers 03 7AX, 067EG I and 03 7. These valves have been identified as used in N-Stamp and/or safety related applications.
(iii) Identification of the.firm supplying the basic component which fails to comply or contains a defect.
The valves subject to this notice were supplied by XOMOX Corporation (XOMOX) prior to 2001. 1n 2001, XOMOX was acquired by Crane Co., which is also the parent company of CNI. At that time, CNl, the entity which is providing this notice to the Commission, began providing support for the subject valves.
(iv) Nature ofthe defect or failure to comply and the safety hazard which is created or could be created by such defect or failure to comply The stem for the Subject valve models was identified as being undersized based on allowable yield stress analysis of the stem while in torsion. The high stress condition was due to the high to1-que required to seat/unseat the plug when installed with an Ultra High Molecular Weight Polyethylene (UHMWPE) sleeve material. High friction factor, inherent with this material, causes torsional stress to exceed the upper limit of yield strength of the valve. which could result in fatigue/yielding of the stem, thus preventing the valve from opening and closing while in service.
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MAR. 21. 2018 11 : 43AM NO. 403 P. 3 TELEPHONE (630) 2,,:y--,~uu FAX (630)226-4646
-www.crancnuclear.corn NUCLEAR CRANE NUCLEAR, INC. 860 REMINGTON BOULEVARD BOLINGBROOK, IL. 60440 (v) The date on which the. information of such defect or failure to comply Was' obtained.
Date of Discovery of Defect: 6/5/2017*6/9/2017 (vi) In the case of a basic component which contains a defect or fails to comply, the number and location of these components in use at, suppliedfor, being supplied/or, or may be .supplied/or, manufactured, or being mamifacturedfor one. or morefacilirfes or activities subject to the regulations tn this part.
Historical research of the XOMOX records is still in process at this time. However, we have currently identified seven (7) sites that have previously ordered these valves.
Xom()J( /Tufllne Order Cu:rtoml!:,. otder dote "' Size, P,.l!:ssure Cla,s, Fig, II, c:ustomer Valve Tog#
NQ, OrdetNO. A~sy dwg. dc,te Codec/ass 3 150 psi Fig. 037/1,, CQde Class E-54021 73l2l Deloval 75001*135 ll/1.5/1977 3
4" 150 psi Fig. 067EG, Co.de E-54021 733.21 Delavo/ 76001-134 %3./:J.:J./l977 C/r,,ss3 rransctmerir;c, De lava!,
6" J.SO psi Fig. 087AX Tatldem, 25.'335 Engine cmd CQinpres,:or 7600:1.-:1.29 8/21/1989 code C/ass3 div., Ookleind, CA Vokes Limited, Henley Pork, Suffolk, England. 6 150 psi Fig. 03'1 Trtr,dem,
/112943 Item 2 & 2A 144954 None Or;t. .'ll, 1990 Sizewell "B" Nue/eor CodeC/ass3 Power StatiOl'I, 47W45D-100.3A1 47W450-100.'lC QN.'3255 90N-I.A-747:z0B TVA Sequoyah ((5) YE0418*FD*4), 9/7/:1.990 4 11 150 psi fig, 067 (6) YE54:t.8-FD-2, (5)
YE64lS*FIH)
P,umsy/vania PQwer & HBC-Pl (C1Jstomer NZX32'11 7-20655*1 10/10/1.990 4" :J.50 l)Si fig, 1167 light, su.squehannc: Item # 1, 5.5 & 5. 6)
(6) YE04l8*FD-4), 4" 3.50 psi fig, 057, Safety P-93/'JLL-NZX3676 TVA Chottonoogc, (6) YE541.8-F0*2, (6) 6/4/;1.99.'l Reloted 10CFR2:1 Applie.s pet 83390C*OOO YE5418*FD-4 TVAPOpgl.
(vii) The corrective action which has been, is being, or will be taken,- the name ofthe individual 01* organization resportsiblefor the action; and the length of time that has been or will be taken to complete the action.
Notifications letters have been sent to the affected plants advising them of th~ condition, and recommending that the sleeve material be replaced with a lower friction Polytetrafluoroethylene (PTFE) material that would significantly reduce the required input opera.ting torque~ thereby reducing the risk of failure ofthe stem material.
XOMOX nas been advised to modify design calculations to provide a larger margin for allowable yield strength.
of the stem material to ensure the stem is properly sized when Ultra High Molecular Weight Polyethylene (UHl\1WPE) sleeve material is used.
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MAR.21.2018 11:43AM TELEPHONE (630) :;,~9', j_~ 3 P. 4 FAX (630)226-4646 www.c.anenuclear.com I C,RANEI NUCLEAR CRANE NUCLEAR, INC. 860 REMINGTON BOULEVARD BOLINGBROOK, IL. 60440 (viii) Any advice related to the defect or failure to comply about the facility, activity, or basic component that has been, is being, or will be given to purchasers or licensees.
Not applicable.
(ix) In the case ofan early site permit, the evtities to whom an early site permit was transferred.
Not applicable.
UPDATE 08/24/2017 Crane Nuclear (CNI) has initiated the final phase of the Part 21 research and is currently reviewing over 15,000 microfiche records from the original XOMOX Canada historical archive to determine if any other Nuclear Sites were impacted by the Subject Part 21. The investigation encompasses sales orders spanning from 1970 to 1993 and 2001 to present. CNl e:x.pects to complete the review by 10/30/2017.
UPDATE 10/31/2017 Crane Nuclear (CNI) has completed approximately 40% of the review of the historical archive and will not be able to complete the review by tb.e previously requested 10/30/2017 deadline.
The historical review covers the following scope:
- XOMO:X UK DEVON, ENGLAND -Safety Related and N"Stamped Valves/Parts issued between 1987 - 1993
- XOMOX Canada & XOMOX A&M- Safety Related Parts from 1979-1993
- XOMOX Cincinnati TUFFLINE- Safety Related and N-Stamped Valves and Parts issued between 1970-1993.
- XOMOX Crane Nuclear - Safety Related and N-Stamped Valves and parts issued from 2001 until present.
Note: Parts M.d valves were no longer supplied by XOMOX as safety-related or nuclear after 1993 until Crane Nuclear acquired XOMOX in June 29, 2001.
The following sites in the table below were identified as safety related valves affected by this letter. All sites were supplied to customer Delaval which no longer exists. At the current pace of review, CNI expects to complete the review of the historical archive by 1/30/2018.
~.., -
Qlja!hyClissff,oatlo~
Co~ Ctc:;:;$, tS77 Ed. / No Md Co<l!:C""53,l!l74~!;1./No
>>,,,_f' Cu5tan'li!:r DI,~
e§=
65105 S:tSSS fi1670 Or~~I cu.,,11,,cr Name ls:!.&l D&,.,.I 2S222 tle!.lM'!
Ot!£1n~, PlantN*m*
WA(Do.,.,.,aiowwii:ct.p-J co=P~sc un~~ 1 & 2 Valve,~#
J..0... ~555 SC!"i!ol~~=11-1..:..o.-
si.:~ ll&, "' Pressvre c~:.,, 0,11.,ca...,
V~llr~D~tion G.,037AX:~
m~~. ~~7,;oo1-12!> s*-0,1..x :iso.
Mt ;;i;a;!"ll r,:!~61!. 2!158 Dei.""31 !Col/In~ 6"~~7AX1SO Cod!! C~B. l!l7l Ed. Wi!h 1R'7El52SA_ 6 ot"'1;>!. E-53259 6.:.m ~s Od.$al ~l!v!!!1ar.1El!1'.?1'\'.. ?R~7~.B 6"o371',X'.EG~
Co4ttt=~.~~~ E-63526 73122 Jil:Ol M=I ~Etee:r~ S/N !$~t00-1 thti ...:. c~,~- F.:, oi.nG COO!:Class3, 2~74 !<I,/
Win:erl9~"""" E*G$l7 ~Sl21 281S1 C&-1 Co~P...ltU~l&2 iGOOC~*aS$. 7600!-~ !2)3" f~.oi7 A)l.1214' F;., 067EG1S();o
(:a6.!!C/53, l97~ E'1. /
Su'M'le, 1!175 A'd<:( s-~s,ss '!'!6! 28321' Daaml M.:l:an,;IN17..,... Pt,lw!,' Pl!w. u=i &l. s~~,.o-o 11~16" f,:,, 0,37 ;J1'1;G~r,;,o,n CO~Cl-3,197~ Ed./
E*=~ ,liOO:.-~.s. ,$00~-:!$G =
~-
i!unml!fl!176J;dd. 1~;.~ "2!!91 llel.""'I =n,;h,:Peo,!<Unl:,:,i&.2 (2) 3"-03715/Jl;. [Z! 4",QS7 IVA, IW<>>/1!k:\IMPl'i'*'!,~ N1,1;!=
N-CI.J:i1il!.~977 Ed/ ~ llo':h-~nc;elfcQ~tc-NoA"'1. &!iSS s1Sss ~ ~<;rnplerion 77K61S?O:I06 ll~IS"~<'0~7AXT-Page 3 of4
MAR. 21. 2018 11 : 44AM TEI..SPHONE (630) 2~9*.. 4~ 3 P. 5 FAX (630)'22.6-4646 www.cl1llle.nuclear.com NUCLEAR CRANE NUCLEAR, INC. 860 REMINGTON BOULEVARD 80LINGSROOK, IL. 60440
.'Ol'DATE 01/20/18 The historical research is complete. Our review of the records from 1973 through 2001 identified 25 valves that were supplied with a stero~sleeve material combination that could exceed the upper limit of yield strength of the valve, which could result in fatigue/yielding of the stem, thus preventing the valve from opening and closing while in service. Those valves were supplied to:
Customer~ Site:
Northeast Utilities Millstone Houston Lighting & Power .South Texas Project Niagara Mohawk Nine Mile Point '
Transamerican Delavel Oakland Power Systems Rocky Mount Bechtel Energy Corp. 5 Miles West Wadsworth Pennsylvania Power & Light Susquehanna NY Power Authority Fitzpatrick TVA Sequoyah Ornaha Public Power Ft, Calhoun
.Notification letters have been sent to some of the affected plants advising them of the condition, and recommending that the sleeve material be replaced with a lower friction Polytetrafluoroetbylene (PTFE) material that would significantly reduce the required input operating torque, thereby reducing the risk of failure of the stem material. Crane will complete the :o.ottfications to the other sites no later than 2/9/18.
Ul>DATE 03/20/2018 Crane reviewed diagnostic testing of 106 XO MOX plug valves for tne purpose ofvalidating the assumed torque values specified by XOMOX guidance. From the review of the diagnostic testing, we determined that on average, the actual torque required to stroke the valve (also referred to as the "break torque") was approximately 56%-67% lower than the calculated value based on the UHMWPE sleeve material for valves with a 150 lbs.
pressure class. Statistical analysis confirmed that the test results were within a 95% confidence intervaL Consequently, a conservative factor ofat least 56% can be applied to the published XOMOX torque value when evaluating stem stress. Applying this factor to the valves previously identified under this Part 21 confirmed that stress limits are below the material allowable for yield strength. This conclusion is supported by operating
_history (e.g., no reported stem failures) in the field.
Based on these findings, Crane Nuclear, confinns that a condition adverse to quality and safety does not exist an\t that .a Part 21 no longer applies. CNI, requests this Part 21 to be retracted.
- Should you have any questions regarding this matter, please contact me, Joyce Hamm.an, Director. Safety &
Quality at (678) 451-2280, Burt Anderson~ Site Leader, at (630) 226-4990, or Samson Kay, Engineering Manager at (630) 226- 83.
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