ML20062H670
| ML20062H670 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/07/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Fraley R Advisory Committee on Reactor Safeguards |
| Shared Package | |
| ML20062H675 | List: |
| References | |
| NUDOCS 8008210206 | |
| Download: ML20062H670 (1) | |
Text
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\ .... ,/ August 7, 1980 MEMORAflDUM FOR: Raymond F. Fraley, Executive Director, Advisory Committee on Reactor Safeguards FROM: Robert L. Tedesco, Assistant Director for Licensing, DL
SUBJECT:
SEQUOYAH Utili PRESSURIZER RELIEF LIf4E WELD REPAIR Enclosed for the information of the ACRS are 16 copies of a report, dated July 25, 1980, that contains an evaluation of the differing professional opinion raised by Mr. Joseph Halapatz on the adequacy of a weld repair of a pressurizer relief line at Sequoyah Unit 1. This matter was discussed at the July ACRS meeting and reported in the Committee's letter dated July 15, 1980. This report contains the peer review conducted by Research contained in a July 24 memo from Larry Shao. Robert L. Tedesco Assistant Director for Licensing N Division of Licensing h cc, PDR i Docket Files (50-327/328 p) COMTMUS Tgis DOCU pgES 6j POOR Q - u i w 00MTNNS THIS n~' - POL' 8 008210208 1 --
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July 25,1980 MEMCRANDUM FOR: Harold R. Denton, Director, NRR FRCM: Richard H. Vollmer, Director, DE l SUSJECT: RECOMMENDED RESOLUTION OF DIFFERING ROFESSIONAL l OPINION CONCEF.NING REPA!R OF PRESSURIZER RELIEF ! PIPE AT SEQUCYAH UNIT ONE I l I have conpleted my evaluation of the differing prefassional opinion which was raised by Joseph Halapatz on June 25, 1930. My evaluation was based on the information pr?sented by Mr. Halapatz both in his June 16th memcrandum and a
" umber of background memoranda. In addition. I have the benefit of comments by "essrs Smith, Gamble, Pawlicki, Noonan and a peer review conducted by Dr. Shao and his staff from RES. Many of these memoranda were included in
;csvious correspondence but I will include them as an enclosure to this r:randum for ycur c:nvenience.
- dditional focus on this differing professional opinion was given by the ACRS
- nd v.as discussed in their recent Secuoyah memorandum to the Chairman. The July 15 ACRS memorandum stated that the Committee did not believe it likely
' hat tLe . ald repair presents a serious hazard but that evidence on the matter cocid be improved.
VA Scs ?erformed additional investigative work along the lines recommended by '.tc ACFS letter. The results of this work were revie.ted by Fessrs uscara
- nd Ser.73n of RES during a recent visit to TVA headquarters office and the repurr:5 plant site. This additional information e.as included in forming the basis for the conclusions and rec:mmendations of the peer review.
The peer review of this matter, ccnducted by Research and described in the July 2t emo from Larry Shao, concluded that the pressurizer relief line draw-baad re; air 1) did not penetrate the pipe weld so that hydrostatic testing is o: ne:essary, and 2) did beccme sensitized and thus cculd te susceptibel to ISSCC in service. They recommanded that the matter be .Mscived by ripuiring a;g in;ed neervice inspecticn in accordance with reccamendation given in N'JREG-3313, 2 vision 1 for service-sensitive r.onconforming lines. Although the line in
'; : tion is not " service-seasitive" and NUREC-0313 addresses EUR lines rather
's ?':R lines, I believe that in:13.entation of tFair r+c:r .endation is i :r; riate and .culd rovide high assurance of the continued intagrity of this
' ne iuring operation. This su; ports my July 2 :~3 to you in s ;ich I tantati.'ely ri::~~2nded aug er. tad inservice inspection as an appropriate resolution of this 1:ter. I chculd note, '...ever, t"a "r. Malapat: states in his ero of July 3
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Harold R. Centon "Given TVA's statament of the safety implication involved, viz., that failure of the repaired piping could lead to an uncontrolled bicudsun of the resctor coolant system, aug ented ISI .could ap; ear not to provide the necessary assurance of safe shutioun. lag :nted ISI t; auld :ddress failure in t:r:s of sicw iceking cracks, a circurst:n=e t;hich TVA ap;arently did not h:ve in eind when concenTur. :nce rer:rt !;CR
.d:P-79-5-3 was t:ritten."
If ycu concur with this resolution, ..a road to :o ir..*;ra "r. '*:i ;st: of this
- cisicn. In additi:n, UE uill :vpply ~3L :.ith th: :;;r:;rista r: .fr: :nts for tha !ccucyah Tech !;ocs to i' ,'1c ;nt th2 v; :.. tad i. 3 2cs !ce !..I, :-:f cn.
"a .:111 :1so ;revide an SER f nput which will t:!c a T!c.:1 s sff ,:siti:n in this 5:tter.
If you wish additional infdrr.ation or discussion en this :tt:r, I rt::1d be hz;;y to set up a reeting betwacn you :nd :ny or all of the principals in this ir'/Osti E: tion. OrV nl s& *d by: 7' ' .:t E. W" .a
?.ich:rd H. V llr.ar -
Otrc: tor
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-d* ! MASMINGTON, :. O. 00$$5 s.s k,N,/
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... x e . .... .....u- m MD'CFJNOUM FO?.: L. 5. Ru:enstein, A::ing Chief
'ign: Water React:rs 3ranen No.
Oivisien of ?- jec: Managemen:
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- 5. 5. Dawlicki, Chief -
Ma ariais Engineering 3rsncn
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- ian: ' tame: Secu:yan Nuclear Plant Su:: liers: Westingneuse; T/A Licensing 3:2;e: CL Res:ensitie Iranca anc P : ject Manager: LWR 2; C. E. 5:anle Reviewer: M. L. Scyie *
*e:ues:ec :=:le:fon Oa a: Decem er 7, 1979
- sseri::icn f Task: Use Of Par.icn O' Later Accenca Of Secti:n X:, ASdE ::e Review 5:a.us: Cem:lete Ouring ::: fune:1:nal tasting at Secucyan Nuclear Flan:, Unt: Nc. 1, a pipe
- anger failec :: slice anc causec ce six-inen ;ressuri:er reif ef iring .
un: erg: piasti: :sf:r::a:icn. This ec=rrence was re:cr.ac = =e Office of
- ns:e::icn and Enf:r:scen: in Ncne:nfor.ance Re; r SWP-79-5-8.
The ced ermec ;i:e was sucsecuently returnec t: i.s recu1 rte sna:e by a draw
- ead nel:ing e=ni:ue (weld snrinkage stresses were usec :: e-align me
- 1:ing) wnfen .vas cualifiec by the a :11 cant. After =eicing =e welc area was examinec by raciegracnic and licuid menetrant insce::icas in ac: rtance vi:h ue recuirsments Of me ASME C ce, Section !!I an ty an ultrasonic ins:e :1cn in ac=rtance wi= ce recuirements Of ee ASME C ce, Sec: ten XI.
The ;1anning and :e 'Or ning Of te nondestructive examination Of =e Secuoyan Nu-ienr Plan: is beine cased ucen me ecition anc accenda e' Section XI of ue AS4E : ce Orcugn :ne Surmer 1975 Accenca. This accenca recui es cat after e: airs ty seicing en ce reac=r = clan: ;ressure cuncary have been
- =:letec, a :ressure .as: shall be :e ':mec in ac=reance nin te ;r:visiens f :'G-!CCO. T/A nas recuested :emissien :: use =e ext:::icn ' :m :ressure testing ina: is :etailec in '# *400 Of Sec-icn X:. ~his exem::i:n "frs; a=eart in :ne Sc:mer 1973 Accenca of ue ASME ce.
'he Oc=:er 9, 1979 eci-icn Of te I E:.AL 1EG'5 ?: : resents an acenc=en: .:
10 0~; Far. 50, ! iC.!!a, 00ces anc i .ancar:s,' un = lii:ws me use :f
- Orti=s :f Tatar sciti:ns anc accenca :f =e ;5NE : ce Iec icn X!, su: ject =
!=revai of me . :-iss :n.
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e 'e V TENNESSEE VALL.EY AUTHORITY c>amaccGA EN'etssEE 374:1 400 Chas: u: 5: ee: *cus: !! Ja=uar7 24, 1980 Oire ::: of Nuclear lasc:c lagu14: ion A::en::.:n: ?.r. L. 5. Ruoans: sis, Ac:ing Chiaf
'ight ~4a:er lasc: ors 3ranen No. 4 Division of Projec: .h agemen:
'J.S. Nuclear Regula:ory Commission
'Jassisston. C 20555 Laar ar. Aubenstels:
- :he Ma : : of the Applica:ics of ) Docks: Nos. 5C-227 To essee 7411e7 Au:ho 1:7 ) : '15.'
Cu January 16, 1980, a :-- as held ar, Sequevan Nuclea: Pla=: vit: NRC-NRK Consui:a=: k!" .w.. Oustafs M 72 *--21337 -- " ~#Is - velis == pressurize: M' =d -t-t-c. 5-* M :his mes:1=g, ?.:. Gus:afson requested addi:1cual inf=rmatics vnich was set availa' ale a: :se plan: si:e. I=ciosec is the reques:ed informa:icn. 7ery ::uly yours, "Z5NESSIE 7AIJ 7 L"."EOK!"Y
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Nuclear las Ala: ion and 544a:7 Inclosure l l . h8 $
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DRAW BEAD ALIGtCE G WELOS 2 meeti g was jeld :n knuary 15,10'0, te:.een Rey Es:ar::n :f ;g;.;;;; an: severa, i m :esign anc constructicn pers:nnel. The foll:winn in Or a:Mn was pr: viced :: ltr, ks:sfs:n ::n 3n-f rg :ne dr:w :ead alignment welds On :ne pressuri:er relief line:
- 1. A drawing cf =e weld ar n.
I. The ei ing :recacure an: 2e : :ce:u e quaif fication.
- 3. *lesui .s f =e I rauss tes: :arfer- e: :n
=:r.u c .
4 Westinge use s:ecifica:icns en .4a:ar :nemistry.
- 5. Pipe :encing ;r:cecure.
- 5. The UT taseline scan f:r eacn weic.
- 7. Certified =aterial test rescr: (C'CR) for :ne :i;e.
- 8. Special ins: vetions from Engineering Design for this car.t: alar weld bead alignment.
- g. N:E results.
!n anti-icn, r. hs.afs:n re ueste.! infor stien that was n:: availacle a:
- ne time of ne meeting. The re uested inf rmatien is c:ntained in n e fellcwing :is:ussion. -
~
Circums zeces tecuirine Use of Craw Bend and Discussion Of Stress Ana1vris Nring ne n:: functiona! test, a pi:e su:00r: providing restraint in ce ic:aral cirection failed = slice as casigned, restraining me piae in :ne vertical dire::icn. The restrain; is lecate: a: joint 23 sh:wn en :ne sket= in enclosure 1. A c:py of :ne restrain; cesign is snewn :n enclesure 2. The max' mum antici0ated vertical movement a joint 32 during normal caera:icn was anticipa:ad ::Ube 2.27 inenes assuming a worst case oceratine tem 0erature of 553 F. The het functional test hac proceeded l :: an ceirating tamperature of appr:ximately 550" F at ce time of cisc:very i cf d e Scunc u: support. The U-col: wnica restrained ce pi:e in the l vertical direction was caflected approximately :ne inch verti:211y. I i i In order :: determine :ne stress levels cut = ce bound sucocrt, l an analysis was run with de piping at 550* F and a vertical restrain; installed a: jein: 33. The vertical restrain: was free fer the One-inen vertical movement simulating the One-inen cef:rma:icn Of the U-ccit. The s: ess levels f:r the joints snewn in enclosure 1 are ta ulatec in l enclosure 3. These s: ess levels are belcw me ASME, Section !!!
- allowacle s . ess f
- r nonrepea:ac stresses as defined by NC-2511.2(f).
l That allewable stress for.A-3757315 is 50,0C0 lb/in . Pressuri:er relief nc=le leads f=r tais anomaly load case .ere f:r ar:ed = Westingneuse for review :y enciesure a and were ac:r:vec by enc!csure 5. . Enclosure 5 ;ives maxi =u= s: ess a: nece 13A during lan: = era:ica f:r j eccasional icacs. Node 1".lA is wi hin five incnes Of cth craw teacs. l l l i
e 's f Raticu:1 5:rettes 8esitual stressc: are c*nsi ered :: be r:J gre::er th:n the stres:es in a re:si- :: ta:e :21 Or in any :her ..el: in the sy::.c . The na:ur: :#
- nes: str:sses at tne inside di: e er (ic) incute: y weic'rg are ::nsidered
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a:ver:e! affe: :ne material's susce::stiitty ::..~J:Ess's"::r :sicn Ors ain; (*G2:~;. C:n=res:ive strasses .re kne' n :: nave a mi-i;a '*; effe: :n 133~~; :nus, we :; no have stress:s wnien can cause :32C". wee- ?- ut *aI:ula-icn 'er Or:w 5and :.e 3 4-
- 1. "aximum hea; in:u: used :n :ne pre:r:cu::icn ::cku: wni:n :assed a 5 rsuss :es .
Am:s = 16CA Vol:s = 1?V Travei 5:eed = 3/4 in/ min = T5 Hea- in;u: per in:n = Amec X /:! s X 5- .
,ravei e icee: Inim1n
= 147 X *$C* t "O e..e U./: Inimln A ..v
=
179.2 kiic.' ules
- 2. Ac-.a1 hea: in:u: used fer procuc ion welding.
Ames = 90A V:1:s = llV T3 = 2 in/ min Heat in:ut per inch = llV X 9CA % 50 2 in/m:n A 10C0
= 29.7 kilojeules Thus, i: can be seen tha: the actual heat in:ut for ea n craw :end is well wi nin c:nsidered ac:eptable limits.
Antici:ated Oxveen 0:nten: Area Of ::ncern is located in :ne 5-inen, schedule 150, vertica! pice run leacing :: :he pressuri:er relief valve a: an eleva:icn ar,:r ximately level nith te ::: Of :he pressuri:er. The envir:nment is satursta: s aa= a: 550" F and 2c85 lb/in'. l l l
s a Based en the bes: infer =ati:n avcilable t: us from Westingh use and operating utilities: -
- 1. "axtre Oxygen =ntent in the rea =r = lant gater is ::n:rciled
- less : nan 0.1 ;/m at e : era:ures a cve 180 F Oy s: avenging with hy rs:ine.
- 2. Curing ;c er =eration, the residual exygen =ncentrati n will no: exces: 0. 005 ;/.... .
- 2. The hignes: cliculate: Oxygen =ncentration ex::e::ed in the steam 1: iess can 0.2 ;/=. '
. E?9! infera ien gives 6 p/m as the threshcid value belew wni:n j
!G200 wii' ne: oc=r in 215 stainless steel (reference SI rs=r:
No. NE:0-22750-6 cated ,1cvem:er 1979, "Ai:ernate Alley for SWR Pipe Applicatiens, Thir: Semiannual Progress Report.* 1: ':2 Oneref:re te ::n:luded that the Oxygen envir:nment is not sufficient t: ;recu e !G2:0. 5a.- a r
- M sed 09 :he f:re;:ing dis:utsi= and the infor 1. tion given 2 ." . '
Gastafs:n at ce 5equoyah eeting, ne f:licwing =n:lusions may be + reacne^ . I
- i. Intergre.nular stress c:rr:sien cracking (!G3CO) will not cc:ur becausa:
- a. Satisfac.:ry results of an ASTM A252, Practice E test, on a :::ku: Of a wcrst case situation indicates that the t material (215 stainless steel in the existing =ndition) is not sus:e::able u IG3CO.
e
- b. Residual s: esse: pr:duced in the weld area will be !
c:m;:ressive and, =nsequently, will not c:ntri::ute to IGICO. {
- . Envir:nment for IG3C dcas nc exist cue te icw exygen =ncen-tratien.
- 2. Stresses ::r:cuted by the draw bead techni:ue are =nsicerad to be e uivalent u : nose in any cther weld in the system and do not acve seiy affec: :ne Secucyan piping analysis.
T'/A ::ncluces ca: ce sucject =ndition will no: =mer: mise safe
- era:ica f =e plant. Furtnerscre, we nave me: Or exceeda: all licensing and =ce ::mni=ents for Sequcyan.
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' "' TC.NNESSEE vat.t.5Y AUTHCR!TY moxviu.t. men (nsr.: s7.,o.,
'a'10C126,400 C :::ser:: Avenue fSy 20,1979
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, Ele::-i: C:r; r::i:n P:s: O'fice bx 255 Pi t:stu g , Fer.nsylvania 15229 Attantion: 14r. M. A. Stan:
Cantie-en:
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. . a i:2".t.O :in Du-ing het functic:::1 testing ct Scru:ych ene of the supper:s en the ; :ssurizer i
r: lief ipin; sci:id and v::uld net e-:ni: fra: ::veran: of :he Otpc; ther:.' ra, 5: 02 yicitting :::ur-ad in the piping. He nave calculc::d ::: cats and fer::s f:r the ;lessurizer n==le f r the ta-:cr:tur. transient which result:d in the 5:nd pip:. The pipe was assunted to act elastica 11y: :ncraf:re, we believ: that in'tse 1:acs are ::nse-vctive. 812a5: rav!cw fer at: ptability the f 11 cuing nc=le leads whi:n are in local c:ce.:ina :cs. F.s(t'as ) Fy(Lbs ) F:(LM) Nx(F:-L5s) Hy(F:-Lb- ) Mz(F:-its)
-442 16,202 992 -20,257 358 -13.56' Your extadient re;iy will be a;orecia::d.
Very truly yours,
..6L.6.LA?a;
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4nba.;' Orvrie-* t e-n d8 'iy L. t!. Caist O. R. E n .ers en , Chie f
;'. :henic:1 EngineeHng D :nch
- Mr. R. E. Ljecn e;,/;p'
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/,00 C:= cree Aven':e, UTC C125 l . j I;nexvilic, Tennessee 379C2 ,>
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L i L :dt A:: lied te Unit 1 3-essuri:er Relic' !!c::le . The 10:ds f:r the U:it i pressuri::r relief ne::1c cresented The loads in the chove ., r:f:r:r::d ictier n:ve been ev-lu:::d and are ac::-tabic.during he: functi:ns.1 :t::ing. ll r:sulted fr: . a schad relief ;sipe sup: r:!"cr -he evalu: tion the loads were!;h :::;a
- tnsnditi:n ' :lic.::Mos for primary clut setendary stresses.t.:cre recuid be ,
en the f atigue li:e of the ne::le will n:: be effected. ,l cenc:rning the evalustien, plcasa centzet =c. b,. 2f y u have any question: . . . Very truly yours..e. ,o.R,.- . i.f e
,JESy a, .C .a ua C.3.1
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" Tennessee 'la'. ley Autacrity Projects .
6.'... t ..FC y f ?'* "' j;K^iT REP'.Y :: ** :=pw I a .,a.; t , n., . *:.. 0. ,....sw .+ . . (. , .
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. c, ENC'.05URE 5 MCOE 12A 103 37RE35EI
?:em'nal Stresses ib/in 2
- 1. 31 :..::.-m 222
- 2. 3ravi y ( W) 159.5
- 2. Acn:rtal Thermal W/PRT 1419.5)
) Use wors:
4 Normal Thermal 1507.1) thermal and
) cole spring
- 5. 0:10 5: ringing W/PRT 2225.5)
)
- 5. 5:ar::: Thermal Moda W/PRT 2?45.a)
- 7. OBE.XY: L:cp A Modes 1 :s 17 258.3)
).use wcrs:
- 3. CBEY : L:co A tbdes 1 :: 17 802.9)
- 9. Pressure:. Stress @ 2?85 10/in2 design 2,343 lb/in' -
Intan'sifi:a:ica fact:r is 1.8 f:r tu : welc. Sum of all stresses fer the ateve load cases: 9 228 - 150 - 2225 + 2447 - 804 + 2943 = 9813 lb/in' nominal 9515 X 1.3 SI.: = 17,572 lb/in 2 Allowable = 1.8 Sh for oc:asional loads 8 Sh for A375 TF 315 at 550 F = 16,700 lb/in 2 All wa:ie = 1.3 X 15,700.12/in
= 20,240 lb/in' anc stressas in this area are ac:a :aele.
, se ee
a n. Enclosure 2
. .a *e e,.
. 8, UN!=ED s7ATEs 5 f. . NUCLEAR REGULATORY COf.i?.t!SSICN ns mcTee c. :. : essa
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... i e 4 Ma:ariais In;ineering Bran: .
Divisi n Of Sys ems Safety
" E *.*1 : J. Hala:at:
N'a:artais In agrity Se: tion
.va :ariais Engineering 3ranen, 053
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s.ei. . .r.= r- i P e. RI.:ET.I'i I: Me=randu:n R. M. 3astafsen :: 5. 5. etwlicki, cated Jan. 25,
'!20: Su: ject . "Tri: Re::r: Of Visi: :: Tennessee Valley Au:n=rity Secy yan ?tuclear Plant, 'Jnit-I" ave reviewed ::c=ents reia ed : :ne Secu yan 'Jni: One eld : raw:eac realignment f a 5" pressuri:er relief si:e nnien aas :ef:rmec caring ne functional testing.' These ::cuments wert previ:ed f:r my review at my rt:uest.
As a resul cf my review, : ree:::: end ina :ne .Vateriais Enginstring Erzncn
- efer its'ac::::ance Of Me t air, as pre:: sed in tne reference cem:rancum,
- encing the :evelce en: anc review of additional infer .atien icentifisc in
- ne at:aen: ent. ?'y review a: dresses Me tex: :f :Me reference memorandu:n:
~he xe-ex' :n:::gra:ns : :vicec .'IRC as formai documentati:n of re::r:
s.:::ceting ac::::ancs Of :ne re: air are c:nsicers: :: :e *criniess with ss:e:: :: pr:fessi nal metallur;ical juegement. Ol Z.723 J. Haia:at- y Materiais n- ri:yggetion Matariais :..gineer agranen, 053
- w/ enc 1:
J. <ni;n: E. Gam:Ie
- d. 7:nr3c
- 4. Sus:sfs:n M. Ecyle (s - L,.t /I c.t
, g as f c1 <- ; f aa 0
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n..e s.a.,,.. .,.
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The weld ;r :ve inlays were mace ditacut iner gas tacku: Of :ne :i:e !;. While it was intanced that ne wall not be fully pene:rt ed, in the case of
- ne :::ku:, newever,1 was fully ;enetrated. Can it be ::nfirmec :na: :ne 3r:du::icn re: air was not fully ;enetratac?
The a:sence Of a ;as backu: caused the : surface uncerlying :ne .eid ;rteves
- :s ex:csec :: :xidatien. If :xidi:sc bey nd a tem:er fii=, sa:n surfaces are not necessarily : rresten resistan; and may actually rust and sl ugn Off in servi:e. The :e::n :: wnica the material enemistry is altere: ty :ne 4
0xica:icn Or cess is refle :ed in its res:ense :: the ASTM A-252 Methoc E test. This may ex: ain any Me:n d A indicated sensiti:stien, Me:ned I passac
- ne material. :n view of :ne c:nsecuences f material failure, ::vicusly more
- etafie: ?ttali:gra:nic examination is in Orter.
Wita -es:e:: :: -he ecge : racks etservec, since :nr:ugn-wall metsiiegra:ny
- is:1: sed sensiti:ation, the actitional metailegra:ny snculd ::nfirm weetter the ec;e Ortexs are tensile cracks or caused by intergranular ::rresien.
Wi n ne :: surface ::rresion 3r: duct sl:ugned :ff as crue, the material af s-
- lesec as sensi:1:ed by Method A test wculd be ex:csed : a s eam envir:nmen
- ntaining as cuen as .2 ::m Oxygen, the ;ostulatec enemistry. Ac: : ance
- : rt: sic'n :ss:s in water, as stated in tne Gustafson memoran:um, may nct .
ne:essarily :e valid, since the ; stulated xygen ::nten: Of rese::r :::ian:
.a ar anc :ne steam ;hase in :ne :ressuri:er are no: :ne same.
- 30: ears :vicus -hat NRC ac::::ance of the re: air sncuid be based On :ne examina:ica of latert::ry sam:les. Metallegra:ni: : :nni;ues are avafia:le.
One use :f :ciari:sc lign:, for exam le, nien :revice f:r =cre tecnnically , , tena:Ie e:21 urgi:si fuegements.
~inally, attenti:n is : ailed :: :ne ma::er :f ne:ner :ne ASME C ce :er:1:s -
- ase etal e: airs f Mis ty:e, since the ealignment ;r:cedure incluce:
fr'ncing ati: gre ves exceecing I/3 Of :ne ,aii :nickness f the ;i:e,
- See NE 2529).
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