ML20085A660

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Forwards NRC to Util & B&W 771005 & 07 Ltrs Re Depressurization Incident at Davis-Besse.Assigned Responsibility & Suggested Content of Sections for Incident Rept Input Submitted.Wa for Man & Computer Hours Requested
ML20085A660
Person / Time
Site: Davis Besse, Crane  Constellation icon.png
Issue date: 10/11/1977
From: Lauer J
BABCOCK & WILCOX CO.
To: Robert Davis, Douglas R, Tulenko J
BABCOCK & WILCOX CO.
Shared Package
ML20085A661 List:
References
TASK-06, TASK-07, TASK-GB GPU-0431, NUDOCS 8307060646
Download: ML20085A660 (7)
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f,r, l , ;i-5 g cc: R Berchin FJ tcvandosk M ER Kane FR Faist TiiE BABCOCK & WILCOX COMPANY WH Spangler RC Luken [g. g '. 3 POWERG5ERATION GROUP M A '3"# k,. m.l ', .m GA Meyer JD Derosey '* 9 ' To lDI5TRIEU' ,_w TION DL Rice AH McCride [fCC1 . ~.y; CW Bruney .Mt. Vernon 4f 8, t q ne w

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~ " ' ' B&W 1etters S'.T-1573 and Fl.:T-1573 dated Octear 5 and Octder 7. NRC permitted ' DP-9 .;..) TECO to startu: C3-1 agctn. However. TECO is ch11 gated te provide a femal .-I W J report on the incidar.: which includes a detailed analysis of the icng-tern. Y::.4.,.3 E:~ .....2

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'AC ..-js .'. N *R in the exit interview nc.as da ed Octder 7 (also attached).. note tnat the.-;,1.p sG report is intended o peceide infor=ation for the NRC Accident Analysis grtup ;,.~ i.;cr., gg 9:.. to evaluate other ac.cidents.. .t.. v. : :. W :-; ..,e...,........- ~.... - $e. ' u.e..f

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c"-Y. 7. m.. m G Irv n SS, 2. Evaluaticn of reactor coolant system, including ~ ?? a. stresses in the pressure boundary gg i -.. 0 b. evaluation of depressuri:ation transient i h ,1 c. evaluation of bciling SG dry . ~. d. effect upon fatigue analysis I he f., e. jet ispingecent on SG shell i P'. l

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Evaluation of RC pu os including n 3.: sj U. a, cavit:tien de: age to ic,.ellers 4 M b. da= age to hearings

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TECQ A t3' 7 2 fM""':. ~ \\ ..c...:P,,,,a I ( ._ w.= .,;.e J. haac - .w 7.a.e.**. a.... 7rc: pre :icus discussic: rs.;stdlar, Septe.ber 24 depresmri::: ion incident. - g -yvz.- .: j g. ,,,.s.,.... _. .w t. .. ~ r I cc:::sitted to the i. t:cwi=g. 55 _E I TECo h:: W.T . n.. s 1 .j C e....: g RegJired prior to P,c<e 2. Testing of A. P geverr.crz u:Icg a cedifi$::. tid.. d.U" a. g to the onthly St c:z 2.:;s. g] . ; i %is to be Jc.ne siter : .. + : of greater than SCG piis is availsbic. - 2in ster.:2 pressure PC F%.I .r Q..e . b. Re rcired prior to %de 2 - Tes:In: cf tk EIcce ::stic Eclic! (ca pressuri:[ bd. ... ~., -.. -.. ?..!T~.. .;g This as to c cyprox.= :e!y five (5) g=en/clon cP:les s.i:L the iso:stion r.F ,y ralve open. In additter: the prop r cperstic: of the circui: and rotencid cc ,.g.g. be enec :.ed ustc; : =2:2:ed p es,e:c sigasg (.eich bloci 7: .1re closed). - ?;..

c. ' Inst 211stion of reca-&.s to conitor the S.FRCS Systes d=:Ing startup. '..

M~..,^ ...g ~..-, d. Refresher Trai::In a: 57:05 for C.:=rstcrs to be co:pleted on Catcher. 22, hO ,. +.. 19 n.. :n. . :. v. ....:....n.. < -.......w....

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-y ..,r.. . c, Ecte z time delay dreycut -o ins =re they get pici.ed up by. EE5 so tha 5FICS alsr : ~ ~A N . the ce=puter :enen 1: r.cs.es c..4e per secc..d. r-s ... t.%. % W L.. - "i 3. Eer:rdi::: the missing etW ic :t= Elec:re:::Ic Oclief ratee s.ontrol circuit. 3-N j the ht" is concernt.f th: Jon't feel th:at it was s-ira.ge, he::his =.ight hu e.bctn industri.zi <:5; ::e.If we . bn sor: of cong, : ggg.2I! ve have to pre. N.E ten.,z si=it r probic. 'Je told To: shon: the instecti.:= :ha: ce made of all - E0 relar c:blacts to insure that ett fuses sne retsis"::e i:st:11ed as requirc.d. E~:" w

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.brecent of the local,rese; pasticttons for the SFKC3 cr::eeest.s is bein: Lg**,- .. ' = conside:ed. The initial =0 itaring of 2CFs is ce..plete but the p-:;; = will continue until. p s. m_ - 1 ,y.... ; ) hq) 5. ,.?N. j the detailed check to be & st IMO psi is cocple:ed. 5 ~ a.- Q 6. In order w get apprevat t= r ,:2p, we had & cc=: sit to - -u--* r~-., L F- -~ rerort o:: the incident, d.ich ::2::~ include a detsited ss.227n: of the long E' ter effect- (fuei life, fa:@e cycles, eec.). Nst ci ri y why in fier C; terece ssy "L'e are also e: r".= sting to " deter =ine [ 'C;, h, .@y#Mg she:hcr,this transient h:<. := dfec:.upon the <sleulated C: irae ' life of the j'. cc:N nen:s,...... " and in :Le 'second ic:ter tr is s:::ed ti.sc. "There is-h: no clunge in the c=lculated fa:Igue life of the acpone.::. i~ . 1 j ~ .4 A.. - ] The prinry yarpese of tie: re. rt is to p;m iJe iniorce.ie= for (f.c NRCs *.ceide st .Y. \\ Analysis Group hc, icill tar.: f:.c isicr. stion in.r sluatir;. cW.r sceident an.slyses. F.

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Records Center .....*5 -% 1 211 d - %.9 w tlucica F. R. Faist - . "4 N' n~...... .-X -- ,- e 2 2' ~ &d"" Toled) J P Jones Y ~ ' EE on :s cc.J. D. Lenardson" ' ' '. N Porer 7:7 '5 Toledo, Chio 43552 - : J: - J. C. Lewis

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300 l'.adison. Avenue ~~ D. J. Delt.Orotx - E,d'. ? c. ?..,... E. C.14ovak/2c... Q ,;s

Subject:

Toledo Edison Co=pany

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b:.d. .- ;?.. p.,.:... ~.1 3 DEPR255U?.I /,TI,:: EYE;'T OF SEPTCGER 24, 1977 y ..,.%.Q,;y..;. j,'.l ;,. ~ "..' ; 4 geg.m .--':q

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Dear Ir. Domeck:

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W: a 1:s. Our letter c5-1578 dated Oct:$er 5,'1977 advised that E1'.! is reviedng the available ~ grq: data regarding the depressuri:ation event of Septa =her 24 and we.ccasider..at there ge, / E.' has haan no degradatica cf safaty in the pTant. Sy tal+ca of Octcher 5, you have p.7 advised that I;F.C would like more.inforcatica regarding tr.e basis for our conclusiona.

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1 .I. 'The c =penents are designed for forty cycles of a depresgj. atic,n transient in which gg the pressure dr:ps 1cCC psi and the te:ccrature dr:ps E2 r.n fi.,-ten cinutes.this a n

7.,,7_

~ ~".9 4 in 7.5 minutes. The stresses due to pressure are n-t se sitive to 6W [n gse c-cita[4nce the ressure char.se of the actual transient is less, an. e g -'T in ran =s

g ould ge of the generalited transient, the stress effect d
e to pressu

' ;' ] pr ssur tr less than calculated for the eenerali:ed transia. .al.,.c.sh .e ra*a o ._,7. ; M -ar in -9 actual transient, the overall ta-parature change is 1 gless. t c53-j. / .4 TheIt o di arenc=s tend to offset eacn other such that the resulting stresses for 4 . the actual tNasient were no worse.than the calculated stresses fcr the des 1.,gn transient. Il the auxiliary feedaatar t.rbine failed to c a up to s;eed. The design transients. g%~ One steam ga terator apparently boiled d / during the depressurizatica event because C include twent'v cycles in which feedaater fica is Icst.to one Sencrator,a-d e,e mg 3 generator is evaporated to a dry pressuri:ed c:nditicn The intred-- C o p# eg into a dry ster generater is a desiga-cncitien any d,have no haZ

s I. ]

The major cencerii t.hile the stea: generator *is dr/,ts variation in .e,;c a-to-shell tecperature differences. In the actual transient ne s:cas genera,.or s o y, 0,. g short period of tice and the ganerat:r rersined pre:suri:e-. C.ing ,, t eP- ^ proximately 13 =inutes, the reactor coolant ter;erature or:ppcd a tc. o, p; ~ J te:perature drcp was not sufficicnt to cause excessn*e,s res, ce per~:1 zr of the tubes, and is within the established design 11:1t5- ?lc The actual stresses were no uc-se *han 'he ca1c~'. *c 8 s* esses frem the " design transient-W h a hW W'2-e-- and censequently the fatigue usage resulting frc= the ac t.- iransient is the '?' - ' that for the design transients. TI,e predicted fa-i jorone desien cycle of E sa:e as thst of one design cycle of rapid d prc s g fctg = gg fg yi .a 'i startup of a dry stcas generator. There is no c.~n,g. of the componenis. Since the stresses and defoi:stgis resu mg frem design tr:nsient M f 1 analysis aru acce;st:ble, there is no reasca to expcc ovctstres.,1ng or dherial defon.;3 tic 2' in the RC system'due to the cctual trdnsient. tic do not censider n, n ,.... J m, guecacs & w. wet cceiur'r I Cc.c: tes 1867 f,., .y .,a .;.. P *,'.'p.g. :b. -yz...- g :, ;;; 4. .; m. ;;.7,,,.py.,q. g -m.m.5 y -a..... J '.~';" ;;~Wr.-..:L y.' & :-T-,<..e.;;.Gn.;; Sh '{.*,; h.... G.,f, :~.:,. -. .T__ '. 3 ...y:$.'."~.-D: .- -=. _~... >u:.u.- n n.:.;- .x..-- ~ .~ . :~

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,gi.; jf, G.,[ October 7,1977. .. ;- :. '. -.. :.7+ ; =2, :. --- ...v: .g; s ~ n. y .......e-

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-. m. - . =:....):y W ~'.' ;. L i.,. , &,. -i." _,... >.. t r a w ,;,Q conduct a detailed inspection of hangers and restraints for evidence of da= age or*.U [. - [ .-.~..n: de forcation.. ~.. ..... S,;.s..; -.... ~. x .?..-..,.. y s - v. . ~.

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= s:

. p:; ;.u.. r; .!.e .: G. rc r- .s . ~. The reactor 'ccolant pirr:ps were all operated at or near saturatica pressure (A2 and 81- %:r - . ] for abcut one cinute and Al and E2 for about 45 =inutes). There is se:me risk of

  1. f i

cavitation dacage to the ic;ellers and also a risk that saturated stea:2 would cause ' D%3 All four pucos suffered either loss of cr erratic seal in dry bearings and resulting da-aSe. In additicn', radial offsets 'ct:e to cavitatica cay 2

.]

dacage the seals. -Ei'.: .,: 5 flow for ab:ut 1-3/4 cinutes after contain ant isolation valvas were closed. '~ir-E reviewed these coe.diticns with the-pu=p canufacturar and conclu a ^ da= age'is s=all. Disasse.bly and ins;ectica of the seals, hearings, and i=pellers --J 8 Yi have rccc = ended that the pu:;s be instrtcanted to =aar.re shft vibraticn, seal l-9 would not provide 1000 assurance that they still operate pre;erly. Therefore, we ' Q.i,: .s y-5 . 6, cavity pressures. P.C' pressure, standpipe leakage, and' seal i-jection fic.s and - E-E-fM m temperature. Ea:h pu=p has been run for tuo =inutes with this instr:::antation in - '-S-4~ a Mode 5 and the cbseryed para aters sh:tt no indication cf da:!ge. We expect to ?.J E.i E.$E have si=ilar test runs in : cde 3 when the F.C pressure is ab:ve 1200';si...If these ' G.c -i F-?. # rvns also shew no indication of da age,} SCI would than recc=end that the pu=ps may 1lc,"... {k{, y; be safely operated as designac. - ..u... _. /. :-M:. a.c:.:. ~ f;.;z, g'.h l C-eg,-

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.M. X. ; ' -. '

.,. r.c BT,U has evaluated the'9/24 incidant with. regard to its effects u;on fuel perfor:2nce4:M %, 4+ - ~ ar'.d has cencluded that there are r.o safety concerns with respect to the reactor. fuel.~:'P.

~;.:~$:yh,h;T; r.f/;1..j.('J9 ~ l M

.'. :t#j This conclusien is hased upon the following considarations: '... r'-> gh;;

y. '=. -4 Prior to the subject transient the reactor had been c;erating'for ap-: ~...'5R.5:l.='. }

/~:.., ~... -;s ~ ",c? @7 proximately one week at a caxi==n of 155 of rated ;:uert ic=ediately I- :.Y. '.1 f! :{tK.. G.. P r .c. dq y -3 prior to trip the pcuer level was a;pecxt:stely 1C: ef rated power, .. I . fe? 3 therefore. the heat generation in t*;a c:ra (da:ay hea:) during the. [9 : depressuri:aticn transient was extremely Ic.: and si 3ificantly le5S J. J ? ',' ' $YT . i'j S J than that produced by the reactor coolant pu=ps. ~ .lj. - R

;*. )

$$?; 'y The core bumup en S/24 was approxicately 1 EFPD.

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'.Y During the transient the maximu:n fuel red internal pressurelas been ~. ~ M,;-. C '. conservatively esti=ated to have been r.o cre tnan 203 pst greater than Y,0. - l .t ' the minicu: RC syste= pressure; the caxi== fuel r:d cladding te arature y; ^1 was 55C7 The tensile stresses ic:ssed en the cladding as a result of y. . i' the 300 psi ;ressure differential existed f:r lass than ene heur. For

r.

i cladding with icw irractation exacsure ex:: sed to t.is te:perature/ pressure y co=bina:ica no dafor=atien or failure wculd be predicted. [:;/ ~ l Reactor coolant te rerature, pressure, and fic;< rate data obtained during if2. the course of this transicht indicated that there was ne signific nt hes-c: vi generatien in the reacter core; this dat.a f' ther indicates that no y a .-l significant boiling occurred in the core. C-; 3 ..y.:.,.} .Very truly yours, i. T:..:.. g; c. .*?@ A. a:arptenier Project !*.anager 3 'l - a ed' ?-, JAL/hj J A. Lauer, Projcet 1*.anager .d -. &'} . ~.-C ' T.e. s . -... -- m ;.:.: : '. -. 4 ', ? - : ~.w: - =.,.; : - - ':..w;-f+ c ~ -.S. D C-?~l',u: :2..-7.c.W. :.<:.-;.,.,s 's, ': ~ - -- c .:..r.4.. -i ::U..:. * '.T.h..i-ll-+.E..i-:E-: ' :6.M -Wi :=;- S *?.~'n:0. T4.:. I ~~~-M: ,-.. r?. ? h-~ ~~. '. -. ' *

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D. D. Tulodieski P.o.ux t2co.:p.c % c,y a.,:a, N_ __ g"r.i A. II. Lazar

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.,n J. A. Lauer . October 5,1977. Neume: n:04):M4111 - ~ - t ..f:'T R. C. Luken .':. M Hr C Records Center l ~ 01JT-1573 ~ 4*: - ' ~ - ' 3 us a. File: T1.2/123 u

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--f. - - ~ > .M. Tolcd J. P. Jones .s - - 6 . Pwer. n..cer eng enu s.unstruen on. cc.: J. D. Lena.rd:en J. C. Letn .. E; ~500 Hedi.cn Avenue .J se ..a D; J. DcLcCroix - J - ME Toledo. Ohio 42652

X JF E. C. Ncvah/2c h: 1:-.:.

TE^ ..D E. .e., Subj.ect: Tcledo Edison Corsany~ -.c. - < E i. DEFRESS!.?.!ZI. TIC. : E'tEi:T CF SEPTEi2ER 24. 1977.'- c '.. .1. 7,U..'....... :, -. - .m. E.=,. . y,,,.y, Davis-Sessc. Unit 1 ~ .c:. L.... :,,. J.- c. m5 N. s.-_. .. -4. I..'. ' F ' s.., ' U.f."., " W...~k.'..'. v.:- e ,'....z Blif Referc-nce I;SS-14,..'- 51 -~ ....,r! '.1: m:W.. . A.... .1. e T..:w. Dcar l*sr. Dozeck: s;,:s. ,n Mr n;..::.;;*:.@e. : :;C..e ?. ..1. ,. %...i., ~ :.. . ~.... v-n.. g -: '.. .~,. o .- +..: ..g r.s.., ;. :w. .s r, sg .m ~ 3 ....x .. (- B3!f is rcvietting the available data regarding the transient c.$ the evening of-Ms.-.

  • ' ~ ~

~ September 2* in unich the reacter coolant *e ressuad-- 2 fr.. a1 os*. 2.- 0 psig SW - ~. - d to abor. o..rO,pstg in 7.5 cinutes. During this depr.zs: crizatica' or the recovary E .- w s-Per 3d ic=ediately thareaftar, there tras apparently sc:e stem forcatica in the' Y ,q reactor ccalant systec, cne sten ganerat:r sec:..dary side went dry, and the reactor - i-coolan pt=;:s were operated a few cinct.es withe t scal injectica 1:ater. i.f-T.-. -a - . ~.. e This transient d:es not a;ipear to have caused any ex:ess'ive stresses en the press'. Ira ~ PI' - -l.;j I . boundary oy ne rea: tor coalar.t, cr sec:ndary systss tscause it is reascnably close ' to he design transients. l'a are reviet:Sg th:sh areas which exceed desica trensiend * ' P ~~ y.j condi.cns to c:nfira that stress levels are within A5: E Ccda alle::able vah:as. '.*e v , J.; an also evaluating to deter =-;ne whether this transia.t has an't effect upon the N 4 . If" -g cticulated fatigua life of the comp:nents, b:rt this sir,uld be of'no i:::ediate cc :ern. !5D .e- ~ [. The reactor c:olant p.:=s trare exacsed to ccnditions ::* itch could have caused cavitction ): datage to the i:pallcrs, dacage to the bearings, and s::1 leahace or failure. !!cne Y of these things a;; pear ta have ha pened and we feel that the p:.-;:s cay be operated 1: . toth cnly cin:r risk of additi nal da=:ge to the pu=;:s. !!a suggest a serie.s of Id Progressive start-up tests undar cicse observation in ords to cinicize the risk of O 7. furt.,:ering any latent da:agas. This is not considared t1 be a safety concern. - i di-u - a ,j Based u;en our evaluation cf the transient ccaditiens, we do not feel there has ' E:: ..r > j been any violation:of fuel integrity which bculd preclude safe startup. Ho. cver. 6: 3 ve have =ade no evcluation reg:rding effcct upon fuel life, i. =. ti' 4 In su: ary, C'.'1 considers that there has been no d:gradatica of safety in the plant ,i. and it r.ay be c;; crated as designed. As en ccenetic con:: n tze urge progressive V startup of the it pu.y's under cicse observatio7 ~ t p 1 'n Please advisc if.you need fu-ther advice.. Very truly yours ..I, r 12 7 . A. H. Li:a'r. cnior Project 1:anag:r E / - :...;} . (Q 0. *r-Q- y ~ . -M JAL/hj ..,..~..:m. J' A. Laucr Project !*.anager -I 5 -lq The D.Wed & WAnt concar I [n*aNs Irt,7 ~-r.- .e I.

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