ML17252A864

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Letter Regarding a 05/15/1975 Occurrence Concerning the Observation of a Slight Leak at a Weld on a 3/4 Inch Pipe to Socket Connection Between Valve S-47 and Line No. 355 of the Residual Heat Removal System - Indian Point Unit No. 2
ML17252A864
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 05/16/1973
From: Caldwell W
Con Edison, Consolidated Edison Co of New York
To: O'Reilly J
US Atomic Energy Commission (AEC)
References
Download: ML17252A864 (2)


Text

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~-~,=-*~-----11-;a_y __._:16 ~ *is)~ Re~ Indian Point Unit N~~ 2 Docket Uo. 50-2~7 Facility Ope~afing LicenGe DFR-26\\ M~. James P. OiReilly~ Dir~ctor Regulatory Operations~ F!ep;ion )_ lJ ~ S. Aro.mi c EnerP,\\' C<:.)J'.mi~s ;l,.()n 9 7 0 Broad Street - ' Ne'!;/a.rk 1 He:1<1 Jer>~ey 07102

Dear Mr. O'Reilly:

  • 1 P.a.g.e l of 4

~------------- PLEP.SE TYPE OR WR!T£ rt~~.. H*{LY WJTHIN BORDER~ DO -NOT rou: ':i'-1*'-;:t o<*~H SENDING BLANK rrr:~~ accorcl~nee wit}, ::,~~:~uim.ont~ of ~e~;~~-~~-1 SpedC fi¢~tion. £..S.L~~ w~ *<td.~h to intol:'rn yc*..1 ¢f.;;.n ~b.nN**~1~l occurrrat1c8 which was identified on l1ay lS 1 1973 at 1300 hOUr'-$. During the cours~ of a routine.plant status* inspection, ~ slight.leti:k 'i-ii1s ol1Ee:r*ve.d at a weld 011 a 3/4 inch pipe. to socket connection between Vaive S~47 and Line No.

  • 3 5 $ of the )\\e~idu.!li Heat Removal Syl!item.

the cOtH'ICC= "tion is loc~ted on t};*~ oischal:'~e side of "thf: Residual H-2..?.t R~II<*?V~.l. r.:.xche.~g't-l"C, upsti"t.l.ti of Ch¢..(;}:~ V~lve 1338.~. 'rhe t'eactcr-at the time of the occurrence. was in tht~ cold ~hutdown condition at atmospheric pressure. l _J PLEASE iYP!! OR WRIT£ PW\\fNl-Y WHHlN BORDER ~DO NOT FOLl:J

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i I t l { I ! ~ \\ ~,. I ~ <rt. t!l.;14* 1~---v. ~Al),.__::,_ __ 1Fnrn. $?:ND. ING,_A_::K. \\:,.;.:,,;:.'c.;( i )~)~*-""-=-='~---'------- !rt accordance with 'i:.he. requirements of T ec::'Imi c,;i_:i:***;f::f}e.b\\i~ ( ficat.ion ~-,i.,. n;;.tirii::-1tion of the St-1tiot~ ~*t:I.8:*:1.~e*r: **r.i.:rwr : : th(~ Chl'!irmiin of tho Nuc.lear. Facili tics Sn.fety Cornmi tti:~c. h.a.~ t.abm pl4<.~¢. *Mt',.,c., fa.~:;.~J'i of you.r- 0ffic<-"=: wasY*.:a::l;i\\-;.. * ~:C*tified on.May 16,, ig73 of the oc~*i.;i:r*:r"~nr:.-~ l.:-y\\ Hr. \\.r~ * * .ffa.ke.pea~e~ Chief £n.gin~e~r,. Unit No. 2. The safetv implications of the oocur~~nce are minimal in °that the reactor' W'd.B in the cold s*hutd.m*.m COt"lrJi tic*n and depressuri~~d. In addition~ the leak wa~ ~ell within the makeup capability of the Che.mica) a.nd Volum-e tCoritrol Syst~m. Alt.hough iriitial criticality has not J yet takch place~ thi: leakage' even if it n.x.d. been.

  • radio.a.cti i/£,

111c.-i.;s1*0 *t~~v-e been d~t~<;t:ed and ~:::*~r-s'.tained * ~----f~a~~~e~.l.~*-==f_4~----~-----~

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_..,...,.l... "'-.--*..:. ** *.*.*...* --~ >;~.>.gG*E 1!i~~J*-"'".,........,.___ __________ _ within th~. vapor ccintainer resulting in no danBer ~o th~ health ~hd safety of the public, We ~re currently investig4ting the cause of the leak and ~ill. s1,1bmi t the req_uired follow~up I'epo:rit within ~ t~_n ( 10).days~ I Will.:1.;un E. Ct!!.ld,.tt£<.ll, i..h"'* Vice Pre.siDe.nt ~ sfN>; ~ ....., ll>UJtJ,>t~* vhj.,.:i fo r.;.~ fo:mc *:f*'t ;;,.;r.,;;, ~Mfl:Of,....t.i¢. DI& httrl--1 \\'II)<<<>'* h< ~lEASE TYPE Of.: WRHE f>LAlNLY WITHIN EOf~DER --DO NOT fOtO <i'i<;-*-{' ~*HJ ,.}}