ML20085A660
| ML20085A660 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Three Mile Island  |
| 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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,i, .y f V.1 REPORT ON DEPRESSURIZ" TION EVEI.*T - Date 2~ D
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-(.;f The attached KRC letter received Septeder 23 cuttined cernctive actions re.. .,. ... . . .
.,9 quired as a result of the CS-1 depressurizatica event. Eased upon the attached 2 -i .b- - W.J
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.-js effects (i.e., fuel life, fatigue cycles, etc.). This ree,uirecent is sur:n-ized7 .. - 'AC in the exit interview nc.as da ed Octder 7 (also attached). . note tnat the .-;,1.p sG
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- report is intended o peceide infor=ation for the NRC Accident Analysis grtup ;,.~ i.;cr.,
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DISTRIBUTION .
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OCTOBER 11* 1977
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report ready to call to TECO by October 28. P, lease advise iccadiately if.this " ..-. .? " ~ 'C date cannot be cet ' . . . . -. .* .. :..-... . -~;. .. .. . ... . a .;
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EXIT INTERIIEW . . 1Cdl . - 0 IU2*ER 7' 1977
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the ht" is concernt.f th: the missing etW ic :t= Elec:re:::Ic Oclief ratee s.ontrol circuit. 3-N
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, _'. , ten. ,z si=it r probic .
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.brecent of the local,rese; pasticttons for the SFKC3 cr::eeest.s is bein:
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- the detailed check to be & st IMO psi is cocple:ed. 5
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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.). . . . [ 'C;, Nst ci ri y why in fier C; terece ssy "L'e are also e: r".= sting to " deter =ine h,
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A.11. l. czar 4:tober 7,1977 T***"# #5* *
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' 3.."'dN D. B. Tulodicski
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J. A. Lauer - BUT-1579 .
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- '. - d . R. C. Luken File: T1.2 - - ' ' - -
- %.9 Mr. C. Records Center . '. . . .*5 -% -
1 211 d w tlucica F. R. Faist - *. "4 N' .-X -- 2 2' ~
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Y n~.~ .' . . .". ' ' - #:.". > - ,- e
... .; Toled) " ' " '
EE J P Jones on :s . ,-, cc .J. D. Lenardson" ' '
'. N Porer ; .
7:7 J. C. Lewis
~~ -'
300 l'.adison. Avenue . .. . : . . .
- .2:.+
.: '5; Toledo, Chio 43552 -
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c . ? . ., .. . D. J. Delt.Orotx - E,d'. ?
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Subject:
Toledo Edison Co=pany DEPR255U?.I
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. E. C.14ovak/2c . . .
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- /,TI,:: EYE;'T OF SEPTCGER 24, 1977 y
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, . , Davis-Casse Unit 1, . . <
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Dear Ir. Domeck:
*. :m -
.-L:,ay; U. = n". M :. < ~
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- . . - . . . ~
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.' m has haan no degradatica cf safaty in the pTant. Sy tal+ca of Octcher 5, you have , p.7
' '.1 advised that I;F.C would like more.inforcatica regarding tr.e basis for our conclusiona. .-
- j gg
.I.
'The c =penents are designed for forty cycles of a depresgj. atic,n transient in which n the pressure dr:ps 1cCC psi and the te:ccrature dr:ps E2 r .n fi.,-ten cinutes.this a
~ ~" .9
;7.,,7_
4 in 7.5 minutes. The stresses due to pressure are n-t se sitive to 6W [n gse c- - g
-'T in ran =s ould. e
;g
' ;' ] pr ssur cita[4nce ge of thethe ressure generalited char.se transient, of the the stressactual effect transientd:e to is pressu less , an ;
tr less than calculated for the eenerali:ed transia. .al.,.c.sh . .e ra*a o -- - - ._ ,7. ; . t c53- j. M -ar in -9 actual transient, the overall ta-parature change is 1/ gless. .4 TheIt o di arenc=s tend to offset eacn other such that the resulting stresses for
. the actual tNasient were no worse .than the calculated stresses fcr the des 1.,gn transient.
4 One steam ga terator apparently boiled d / during the depressurizatica event because Il the auxiliary feedaatar t.rbine failed to c a up to s;eed. The design transients . . g%~ . C include twent'v cycles in which feedaater fica is Icst.to one Sencrator,a-d e,e . mg generator is evaporated to a dry pressuri:ed c:nditicn The intred-- C oeg 3 .,
.. into a dry ster generater is a desiga-cncitien any d ,have no haZ '
p# I. ] The major cencerii t.hile the stea: generator *is dr/ ,ts variation in .e ,;c a-to-shell -
;s
^
tecperature differences. In the actual transient ne s:cas genera,.or s o y, 0,.
,, t eP-g short period of tice and the ganerat:r rersined pre:suri:e-. C .ing o, ,
~
proximately 13 =inutes, the reactor coolant ter;erature or:ppcd a tc. --
, 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 -
h" design a hWtransient- W'2-We--
; 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
.a sa:e as thst of one design cycle of rapid d prc s . -
g fctg = gg fg yi
'i startup of a dry stcas generator. There is no c.~n,g. -
M 1 of the componenis. Since the stresses and defoi:stgis resu mg frem design tr:nsient f 2' analysis aru acce;st:ble, there is no reasca to expcc ovctstres.,1ng or dherial defon.;3 tic ,
.- in the RC system'due to the cctual trdnsient. tic do not censider n, n ,
.. m, guecacs & w. wet cceiur'r I Cc.c: .tes 1867 f, . ,
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October 7,1977 . jf, y G . ,[
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,;,Q conduct a detailed inspection of hangers and restraints for evidence of da= age or* .U [. [
.-.~ . .n: de forcation. . .... >
. . , , .. .. ~. ~ . . - . . . :. . , : .u .. . . . . . S,;.s . .; - . . . . xrc -
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.~.. 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 #f i cavitation dacage to the ic;ellers and also a risk that saturated stea:2 would cause ' D%3
; dry bearings and resulting da-aSe. In additicn', radial offsets 'ct:e to cavitatica cay
;.] dacage the seals. All four pucos suffered either loss of cr erratic seal-Ei'.:in 2
.^ ,: -, 5 flow for ab:ut 1-3/4 cinutes after contain ant isolation valvas were closed. - '~ir-E a
reviewed da= age'is s=all. these Disasse coe.diticns
.bly and ins;ectica with of the the- seals, pu=p hearings, canufacturar and i=pellers and --J conclu 8 Yi
.s would not provide 1000 assurance that they still operate pre;erly. Therefore, we ' ' Q.i,: .-
- have rccc = ended that the pu:;s be instrtcanted to =aar .re shft vibraticn, seal y-5 l-9
. 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-?. # ,
y; k{, rvns be safely also operatedshew no indication as designac. of da - age,} SCI would than -
..u... recc=end that the pu=ps
~ - may,; 1lc,"... { a.c:.:. .
- .d -
- - . . ..: .. :.M. X. ; ' - . ' -
_. /. :-M:. . .. . f;.;z, g'.h l C-eg,-
., . 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. '
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.. This conclusien is hased upon the following considarations:: ~;'...:~$:yh,h;T;
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Prior to the subject transient the reactor had been c;erating'for ap-: ~ .. .'5R.5:l.='. " ,c? @7 }
~
P r -
'- .c. dq
- proximately one week at a caxi==n of 155 of rated ;:uert ic=ediately I- :.Y. '.1 f! :{tK.. G. .
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 siS 3ificantly le5S J. J ? ',' ' $YT
. Ji'j than that produced by the reactor coolant pu=ps. - '
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'y - The core bumup en S/24 was approxicately 1 EFPD. ; -: ,
p .
- @_q
'.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 %- co=bina:ica no dafor=atien or failure wculd be predicted. y
, [:;/
~ . . .
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'ather indicates that no y
.-l -
significant boiling occurred in the core. - C-; 3 . T:..:..
--...y.:.,.}.&
- . .Very truly yours, i. g;
. c.
.*?@*
A. . a:arptenier Project !*.anager .
?- ,
3.d'l . JAL/hj J
- a ed' A. Lauer, Projcet 1*.anager %
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P.o.ux t2co.:p.c % c,y a.,:a, N_ __ g"r.i D. D. Tulodieski
. ,n J. A. Lauer _
. October . .
5,1977. .. Neume: n:04):M4111 - .
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tNCd,
..f:'T R. C. Luken - -
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01JT-1573 ~ 3 us
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File: T1.2/123 u6
.M. Tolcd J. P. Jones -
. Pwer . n..cer eng enu s.unstruen.son- .-
cc.:
. .: J. D. Lena.rd:en
. . E; .- -
J. C. Letn D; J. DcLcCroix
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~500 Hedi.cn Avenue . .J . .a . . -J- ME
. .D Toledo. Ohio 42652
- X JF '
E. C. Ncvah/2c TE^
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.; Subj.ect: Tcledo Edison Corsany~ - -
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E i. y,,,.y, DEFRESS!.?.!ZI. TIC. : E'tEi:T CF SEPTEi2ER 24. 1977 .1. .'- c7'. ,U. . .' . . . ..-"...:,. -. . -
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Davis-Sessc. Unit 1 .c: . L .. . . :, , . J.- c. ;. . - :: ::.- m5 .m. ~ v.:- e
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. .z Blif Referc-nce I;SS-14 , ..'- 51 *
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W. -:. .~ . Mr T..:w. n;.r.::.;;*: .s.., ; ..@e. :w. : :;C ..e ?.
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.. (- B3!f is rcvietting the available data regarding the transient c.$ the evening of-SW
-~.- .
September 2* in unich the reacter coolant *e ressuad--
. . . .- w 2d fr .. a1 os*. 2.- 0 psig Ms.-.
s-
" to abor. o..rO,pstg in 7.5 cinutes. During this depr.zs: crizatica' or the recovary E
,q Per 3d ic=ediately thareaftar, there tras apparently sc:e stem forcatica in the' reactor ccalant systec, cne sten ganerat:r sec:..dary side went dry, and the reactor -
Y
-a -
- i-
-. . , . . coolan pt=;:s were operated a few cinct.es withe t scal injectica 1:ater. -
i.f-T.-.
' " . . e - .. .
.. - . ~ . .-. .-
-l.;j; This transient d:es not a;ipear to have caused any ex:ess'ive stresses en the press'. Ira -
I
. boundary oy ne rea: tor coalar.t, cr sec:ndary systss tscause it is reascnably close ' #
~ 'PI' -
v y.j to he design transients. l'a are reviet:Sg th:sh areas which exceed desica trensiend
- P ~~
, J.;
4 condi .cns to c:nfira that stress levels are within A5: E Ccda alle::able vah:as. '.*e an also evaluating to deter =-;ne whether this transia.t has an't effect upon the N
-g . If" 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 . ..
- .- ..r >
,j Based u;en our evaluation cf the transient ccaditiens, we do not feel there has ' .
E:: 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.
t and it r.ay be c;; crated as designed. As en ccenetic con:: n tze urge progressive startup of the it pu.y's under cicse observatio7. .
~
Vp 1 . . 'n Please advisc if.you need fu-ther advice. .
.. ..I, r - -
Very truly yours ... 12 . 7 '
. A. H. Li:a'r . cnior Project 1:anag:r
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