ML19101A097

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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
ML19101A097
Person / Time
Site: Hatch, Fermi, Grand Gulf  Southern Nuclear icon.png
Issue date: 04/04/2019
From: Fisher A
Weir Valves & Controls USA
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
53973
Download: ML19101A097 (7)


Text

WEIR Flow Control Weir Valves & Controls USA Inc.

29 Old Right Road Ipswich, MA 01938 USA T +1 978 744 5690 F +1 978 741 3626 www.global.weir To: NRC's Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001 From: Allen Fisher Date: April 4, 2019

Subject:

Part 21 Written Notification - Event Number: 53973 The following documents are included:

NRC Notification Letter - Total 3 pages 10CFR Part 21 Evaluation -1 OCFR21 2-8 Total 3 pages - 1 of 4, 2 of 4, and 3 of 4

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  • IHII.

Flow c6ntroi Weir Valves &:Con!rols*l:JSA Inc;

  • :i9: Qtd. 13191i1:R.o.ad * * *
  • lpsv,ith, MA 01938:

NR.C's Dmcunieht. C:qntrn!De$k . U$A U.S.:Nuclear:Regµiafory Commi~sion i: + 1,9'fo .'(44 6690 '

Washington, DC-2055~0001 F. +1,978741.3626".

  • wwv,,.gi~tifu:weir De?r .$ir .or Madam, This notification, is being: submitted-pursuant. to 'th~ gufd~!ities: of 10 CFR Part 21 to-report- that a*

24" Cl~ss 1'50 GJ6o;'l'°-V~lve. for R.HRS\JV-HX ls9lati9_ri. MOV, El1.5QF068B at 0.e:troit-Edisah _.,.

f=etm r:2*; experieneecf twq: st~m f~iltlr~s~ * * *

  • The,site*- notifieg* WVt lJ.SA:on November :eth: ofthis is$u~ inv9lving,.tw9;.~.t~ms:. W\/;C ()$A h~9 supplied* tl;tese; stems *oh .otders.2Q0l)0262:.j-p:_and::2c:ro1200*1-to, Qetr.oit Edison ,Pb's 4700505700 arid-4701'149217, A, hew stem fai!,ed in service after*ap'pr'oximately 1 .month ir,,

service in valve FQ68B. A repl~cement ster,:n wa~ iostalled:gng faJl.ed soc;>r') .aft(;)r .l~(;)ing _p]aceg:i'n:

servic:e: This secmnd *stem failure .had previously been i.n. service*fot .approximately* three: y.e~rs whil~ installed in sister valve Fd68A. Bbth stent-break~ges qc;¢urrecl*atthe*-trc;insftiqn ~r~c\.tifthe, stern ba.ckseat an_d wete.vi~ualiy iqentk:aE See,,piQtur(;)s .of faill:lre*:in': Attc;1chm~ht A In the: *as.

found condition, the. disc to -stem,connection' appe~rs:to have .lacked' oesign ..clear:ances. The cause of this* cleqrance issue. was cleanin*g qf tbe*:disc:s{.Jrfc16e: where the* disc: rut. i.s: t~c~. welded.

The. material supplied 'is A276, 41 b heat treated'. ahd temp$red. to obtain .(269.-3,tt .BHN). This material was *approved by* Pow.ell* as* an acceptable *alternate tc{the.-origir:iali m~forigf'Af82.

F6(269-311 BHN). During original Part :h eValu~tioh, testing of the :st~m materi;3I :reVeale.d.io.W-impact values. and reflected effects oftemper*embritt1e*ment *other p0ssib!e* contriolitorsJo* the failure were transitiqn* region at stem ba~kseat ~n_d the valve service conditiomrwher.e vipration due to throttling has* been experienc:ed.. It was* de~erminet{ that* although temper-empdttl~ment.

to and othE?r factors* maY:have contrfbut~d *the .failures, that the.lack of design clearc;1nce:.led to.

the failure 0f the stems*.and*was .not i:-eport~ble by WVC*LJ.$A. .However; -after dj5cu$sion§,with De:troit Ed1son, WV.C USA.was requeste.dJo.eva!uate the. failure considerihgJhe-e.ffects of * **

temper embrittlement that Thightlead to futt1r'e .faffµres.

WVC USA engineering is unable. to determine .the: effects of temper embrittlernent. fpr the A~?fJ 41 Omaterial; Powell :engineeri'ng. WgS !3[sq c:Ort$ulted'*ancHher~ are no known *met_hg_ds .t9 ..

evaluate the pote11tial f9r failure-on .the stem in this condition; A.s not~d_ in NRO- lnforrnatioo No_tic_e No. 85-59, tempering .in ~he 70QF-t9 to!?OF r.a.hge is* riotrecommende.d be.c:ause**.it re_s.ults in iow and erratic impact properties anclpoor r~slstanc~. tc;> *~orrosjon ari!:f :str~$$ coi-rosion,fqr 410 stainless steel.

  • _,
  • The stem failures in this case reflected. these low c:ind.erratic irnpa*ct properties based**on-

, mater.ial testing that w.as performeq by'OTE Fer.mi and WV¢ .USA the* A2_7$*. 41'0 materials*.

supplied in .this event. were. tet')lper.ed gJ .t025FJ:tl1~f 1:Q50F, *

  • The* _best soli,1tiori js to .eliminate. the* potential for.temper ernbrittlement l;iy using* a higher required tempering temperature .. The :recomtn').ntji;1tiqn: i~,to; U$e}\276 410 t~_mpete~ *.at*a1 minfmum of 1100F.. This is. als,o* in aJ1gnment with C9de* Case 'N_;:62'-T We,are in tf.t~* process: of updating. our item r~c6r~~ to. re~~9t tfti$ m_inimuqi t~mperir:,£1 re.g11ir_ernent *anq -~~p~qt* tfjis :a.diem to be completed withit'l .one month.
  • we U$A is*.notify1hg, th~ followihtr $it*es:.6Hhis po'!~riti_~f .issqe:s6'*tMat \h~Y *<?an *eY~l~~\idh.e._

impact on,.the.*safe**opetation :0ftlie**pi~fr1t.

  • 74347-~1 O Entergy . PO, tG11 $_969,:S.ited3rancit.G.ulf

'lter:n* Numb$r P_;2f31-206f9ASSEMAOJQU\

. . - -Sterrr,&*,t>lsc, As&.'y, +4'; dy (:1'.,) *sn1ppe:d

-712*a1bf,,

. 0020.005433.:.to.-<3eprgia..Rower: compahy :p.o:;*$N_c;,.1ooaj;~:r2: REV.. *2.,::Site Hatch'* ..

Item Number P00094t9.C,Stem/Dis9 ,Assy 24*-.:~09; Glbbe:Valye*Qty (t), -~hipped 1:0/2$tt9; Q0,20.0069.79-1 o: b_etroit *(=diso*n-:0.qr.np~ny}>'b *47:00.8.46'g9}5:- S.it~r,:Ferflil 2

!t~rn NL!rrtber l?ObdQ455.¢ Sl~m,;8jn.:G~te~V~lv'e*: ~ty '{1fShippecf'$/.2$/t5.-

002oot1.676;;1.0* Oetr.0it'E:(;li$on 'Conjp,ari.f PO 47.01:,12:34.03!Site :Fermi:2-Item N_umb~,r-p600ti45,QCt'Stem ,e1n .G~J~N~tv~* .Qty (1;) $hippecl:2/1'4/1 '~.

002001.3251.;1 0 D:etrqit *Eoiso!:i.'.Company PO :470'1'~30062*' Sife*.iFermi 2.

Item Number POO©o2~3,.stent Glqbe.24in. tpO# *oty ~1) Sh\pped* ~Yt$/JB:

0Q20bt3586~1n O.etroit ~dii:fpn GompanY. p*o ;470*1t5992f:3: Q'0#6i$i~Et .FermU2'-

ltem Number P0.00.0283.Stem Glob'e,24in, 1'5Q#Gty{1) *$ni'pp:ed 11/1'3/Hl,

  • Stem supplied under or<;ler 0020.0l325{.;tQJs *cur.r~ntly itjstalleq ih F06$Aand order:

00200.13586-1 owa,s :deliv$recl but':('.l9,t.ir:1stalle.d,. ,F06$B *vaJve ,has been re$to'r'ed*btDetroit Edison, with.~ stem which h~s accepta[?l~. pr.opertie*sf0tthe* $.~r'.Vice..

Please feel free*to contact niewitii ~nyquestions or. comments*.

All~n Fisher Director-of EngTrieerin*g alien. fisher@niair.w*eir T +1 978'.e:?:'5 8451

,M-+1 252 940 9501;1

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10 CFR PART 21 EVALUATION DOCU MENT PAG E WEIR Evaluation of Deviation or Potential Failure to Comply 10CFR21 2-8-19 1 of 4 Part 1: Identification of Concern and Preliminary Evaluation 1A Identify the source of the information on the deviation or potential fa ilure to comply:

DTE Fermi has requested WVC USA to determine the effects of temper emrittlement in fa iled stems originallyevaluated for Part21 reportablility under evaluation 10CFR2111-19-18.

18 Describe the deviation or potential failure to comply that has been discovered :

Customer has reported 2 stem failures on a motor operated Powell Globe Valve 24"150#

1C Does the potential failure to comply represent a violation of the Atomic Energy Act of 1954, as amended, or any applicable rute, regulation, order, or license of the NRC, including technical specification limits?

If Yes or Uncertain, a potential failure to comply exists check O and complete Section 1F.

If No, check ~ and complete Section 1D.

10(1 ) Does the deviation affect the functionality of items or services provided by W eir Valves & Controls USA?

If Yes or Uncertain, check~ and complete Section 10 (2). If No, check O and complete Section 1E.

1D(2) Does the deviation involve a basic component?

If Yes or Uncertain, check ~ and complete Section 10 (3). If No, check O and complete Section 1E.

10(3) Has the bas ic component been delivered to a customer?

If Yes or Uncertain , check~ and complete Section 1D(4). If No, check O and complete Section 1E.

10(4) Does the basic component deviate from the requirements of the customer 's procurement document?

If Yes or Uncertain, check ~ and complete Section 1G. If No, check D and complete Section 1E.

1E No reportab le deviation or potential fail uire to comply in accordance to 10CFR2 1 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 1F The deviation or ~ ure to comply warrants further evaluation in accordance with 10CFR21. ~

~ ,-

Originafur{signature)

A lie~

Originator (print) f:'-$ker .2-/ ~1r Date Forward this form with relevant information to the Designated Responsible Officer.

1G I have reviewed: Part 1 and determined that the deviation or potential fa"l'ure, to comply should be evaluated based on the basis below for reportability in accordance wi h 10CFR2 1. {Start of 60-d ay clock)

/Z _.PU-

' Design~ted.Be~onsible Officer (signature) 2/8/1 9 Date Initial Due Date:

4/1/1 9 Within the 60-day cloc~ started above, I will evaluate the deviation or potential failure to comply discovered in Part 1 to determine reportability in accordance with 10CFR21 .

~~ 2/8/19 Cognizant Te3hnical Engineer (signature) Date WVC_ 10CFR_EVAL 041216

10 CFR PART 21 EVALUATION DOCUMENT PAGE WEIR Evaluation of Deviation or Potential Failure to Comply 10CFR21 2-8-19 2 of 4 Part 2: Technical Evaluation 2A Identification of the company supplying the basic component or activity which contains a deviatio n o r potential fa im ure to comply:

WVC USA & Powell (design contrnl for spare parts) 28 ~ Confirm the information in Part 1. Note any discrepancies that need to be addressed :

DTE Fermi had a new stem failed in service after approximately I month in service in va lve F0688. A replacement stem was insta lled and failed soon after being placed in service . T his econd stem failure had previous(y been in service for approxi mately three years whi le installed in sister valve F068A. Both stem breakages occurred at the transition area of the stem backseat and were visually identical. In the as found condition, the disc to stem connection appears to have lacked design clearances. The cause of th is clearance issue was cleaning of the disc surface where the disc nut is tack welded. The material supplied i A276 4 10 heat treated and tempered to obtain (269-3 l I BHN). This material was approved by Powell as an acceptable alternate to the original materia l A 182 F6(269-3 J I BHN). During the previous evaluation testing of the stem material revealed low impact values and refl ected effects of temper embrittlemment.

2C Provide A) Technical Justificaiton of Unit Acceptability; or 8) Proposed Technical Solution WJC USA eg ineering is unable to determine the effects of temper embrittlement for the A276 410 material. Powell engineering was also consulted. There are no known methods to eva luate the potehtial for failure on the stem in this conditio n. As noted in NRG Information Notice No. 85-59, tempering in the 700F to 1050F range is not recommended because it re sults in low and erratic impact properties and poor resistance to corrosion ands ress corrosion for 410 stain less steel.

The stem failures in this case reflected these low and erratic impact properties based on material testing that was performed by DT E Ferm i and \/NC USA. The Kl.76 4 10 material supplied. was tempered at 1025F and 1050F.

The best solution is to eliminate the potential for temper em brittlement by using a higher requ ired temperi ng tem perature.

The recommendation is to use A276 4 10 tempered at a minimum of 1100F. This, is also in alignment with Code Case N-62-7.

0 This issue is reportable pursuant to 10CFR21.

0 This issue is not reportable pursuant to 10CFR21.

~ A decision on reportabi lity cannot be made based on the ava ilable information.

~~

Cog nizant TeChnicalEngin eer (sig nature) i-t/1/11 Oat~

Review with the DRO within 5 days of completion Resr:1 le Officer signature) Date' e ORO will finalize the reporting requirements and submit the reports to the NRG and an affected facilities within 30 da s.

WVC_ 10CFR_EVAL 041216

10 CFR PART 21 EVALUATION DOCUMENT PAGE WEIR Evaluation of Deviation or Potential Failure to Comply 10CFR21 2-8-19 3 of 4 Part 3: Conclusion of Reportability Evaluation 3A Basis for decision:

6~J~ ~ ~ J~~~# ~~~ r ~ :zC ~

~~d-4~~2~ ~ " '

3B Number and location of all affected components:

7434 7-10 Entergy PO 10118969 Item Number P_26126666ASSEMAO_QLA Stem & Disc Assy 14" Qy (1) Shipped 7/28/06 0020005433- 10 Georgia Power Company PO SNG10081312 REV. 2 Item Number P00004 19C Stem/Disc Assy 24-300 Globe Valve Qty (1) Sh ipped 10/29/15 0020006979-10 Detroit Ed ison Company PO 4700846295 Item Number P0000455C Stem 8in Gate Valve Qty (1 ) Shipped 6/29/15 002001 1676-10 Detroit Ed ison Company PO 4701123403 1

Item Number P0000455C Stem 8in Gate Vatve Qty (1) Sh ipped 2/1 4/18 0020013251-10 Detroit Edison Company PO 470 1230062 Item Number P0000283 Stem Globe 24 in 150# Qty (1) Shipped 9/ 19/18 0020013586-10 Detroit Edison Company PO 4701259926 C0#6 Item Number P0000283 Stem Globe 24 in 150# Qty (1) Shiooed 11 /13/18 3C I have evaluated the information and technical assessment developed and 0 Th is iss ue is reportable pursuant to 10CFR21 .

0 T his issue is not reportable pursuant to 10CFR21 .

[g} A decision on reportability cannot be made based on the available information.

Based on th is dete rmination, I will proceed with all proper notifications within the allowable tim eframes .

WI/C_ 10CFR_EVAL 041 216