ML18087A002

Crane Nuclear, Inc. - Final Report for 10 CFR Part 21 Investigation Report Notification of Xomox Plug Valve High Torsional Stress in Stem

ML18087A002
Person / Time
Site:	Sequoyah, Susquehanna
Issue date:	03/21/2018
From:	Kay S Crane Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18087A002 (4)

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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