ML20197E980

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Forwards Transcript of 851017 Public Meeting on Containment Leak Rates in Glen Ellyn,Il.W/O Encl.Related Info Encl
ML20197E980
Person / Time
Issue date: 10/23/1985
From: Hoefling R
NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD)
To: Bernero R, Connelly S, Shapaker J
NRC OFFICE OF INSPECTOR & AUDITOR (OIA), Office of Nuclear Reactor Regulation
Shared Package
ML20197E896 List:
References
FOIA-86-20, FOIA-86-A-47 NUDOCS 8605150371
Download: ML20197E980 (56)


Text

{{#Wiki_filter:W October 23, 1985 Note to R. Bernero, NRR S. Connelly, OIA J. Shapaker, NRR J. Huang, NRR G. Arndt, RES F. Maura, RIII MEETING TRANSCRIPT Enclosed is a copy of the. Transcript of the Publ.ic Meeting on Containment Leak Rates held in Glen Ellyn, Illinois, on October 17, 1985. Richard Hoefling, Counsel for NRC Staff Regional Operations and Enforcement g Office of the Executive Legal Director

Enclosure:

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10-26-77 ~ APPDDIX G f ~ SIGNIFICANT LVDCS'IDG 3.. Re:ctd any changes in the valve lineg, at:y leau repaired or other 'f bes' nade, and any event which is nct censistent with no.d cperating precedures. Recer6ed ' _ cate Tine Event P' 7 -j .)l2lSl 0.(.yo o CesM b udawed w l p W u s w. e s,+ +v W L "d'.* u n M */f l i pspJinx cha v&. fw caos i y (-fwooy) e.h a.:9 . n , p.,< a.ss. % d. f hff W fhhh ) ZW Mhs .r, ten fm pp. h .,,b'adoyw Y V h l- ../ ou s k lffY, h Yb. ' '3 Fes.-./'.cWN.s2</ d4 / l inne, pers-<' a,<M./ e sai-t ehd-f }"I'L IGo pwsa, e.,May skyd. O 16 & /2x<Mof b epa 4u p<<sA 6ed l wi A' c w aan g co' u.s< o Jer da, l l es derrie. I r I ' /M Rwet' ks&. cad /c faAm .uy s ,sn & i 1 ~. .~. g3

e wth'mm-*v%v e merehwd:aw.Wms.r%vw#&M.%vs.+s%w{~,.*?gs Qf,,,,,,,;( 6 10-26-77 APPENDIX G SICiCFICT3r r/nc :.lX; 3.- Rcc:rd a rf enr. gen in the valve lineup, a~f leau repaired og other 'f ues' nace, and any event which is not c::r.sistent with nor. al operating precedures. Recorded Date Ti:Te Event BY \\'lh! 5/cpps/ cgruses p~.yays4 7.& I %g p rso q &. l VMcfAV h l gg g go,$ fdf 17fo MCO S/~ f M r & s W Y Orjt gpx f ru o.. SV+' 8 e l i j D 'l p I l ~ S e / I ',m, 62

,= 4 h:m-s'~..-~ws xrm,x.<:,. w,.av >s,.ms m n%;. wa.s., 4 w m sirr..n.n.+3SS 6.1QA,w,;. ~, 10-26-77 APPENDIX G SIGNIFICNfr EVINIS IOG B. - Recced any changes in the valve lineup, any leaks repaired or other 'fiams' made, and any event which is not consistent with normal operating peceedures. Recorded Date Time Event By $l 4L9f & 'R ~ W- % { D N fY 4(6 M

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y 10-26-77 APPROIX G SIGNIFICWT EVDUS ICG B.- Recced any changes in the valve lineup, any leaks repaired or other ' fixes' made, and any event which is not ocnsistent with nociial cperating procedures. e necorded Date Tine Event By 35 /0 ' ash Ja'n e m -edu4 y.Ay 4 7~z.cv CAuk d M og m WS to*C CAuAufxvcesy. A % gg clu/<uf n ssa,k sa~r.de sy.c h A Rv ft<' y, n & p wp v/!3 $.haLap., 3/A I!W Tua 4ct Pig h-d oncre se r L M = tT2 M c</. cJw f6< ~ , t, nL A Chuc( o wp co& 't og t< 1 tupi7MB g<g A. rad d A O L(.da Q f4' g) Y Smy4 at wD .a l- ~ chau,( ha ac,6 c4 ,,,, m ~ Shsy L.4 NS, g,twQ M peu y. No % JM. /Sco CAuh d A b E'Y + d CS m </ Th' nam u.,* Aap. 0 17c0 pa.4 K ad,a;h w oir Aaa',yy S' Decu4x -d W' ,G- = 83

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10-26-77 I APPD CIX G SIGNIFICMT EVENTS ID3 ' 'B., Record any changes in the valve lineup, any leaks repaired or other 'fixas' made, and any event which is not ocmsistant with normal operating procedures. Recorded Date Tim Event By Y@ h* A. .Y Hl Mesrp. Lhdi Gbi~b a M ) Wo ~ d$ e e i y#yseeses ( suft Q m M c5 q esw

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i j ,, & w.y,w e n w,:-.= -a w ~~r % " " ~s* "> * *s" $ $ b ? ~"" W '* 10-26-77 APPDOIX G l SIGIFICANT EVDFIS IOG I, , B. - Racerd any changes in the valve lineup, any leaks repaired or other 1 i ' fixes' made, and any event which is not cmsistant with normal operating pro:edures. Recorded Date Time Event Bv i .3/4 f & vc T y.af & 9c'.sy. fM y t.wo - %d & tt2 ced. SV- ' ?? N Jewd (l't jor- /08) C U & c6*t.( oos) ~ CAa/aa'f M, J tsc so3S (l' 7~-t Ga. Afte & # sad l C4 eau / PZ f3) (sz br'h y p) L Aw, m. C/afud f/w /"*P #'W wx& Pug. pp- /ri-1330 a c9 ye m./uae.. ' pir framdW.A :1 300pg.

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10-26-77 / en G SIGNIFICMT EVENTS IOG ' I.. 'Escord any changes in the valve lineup, any leaks repaired or other ~ B. ' fixes' made, ard any event which is not ocmsistent with normal operating proce& ares. nocorded Date Time Event gy Y k /f'd Z.L/ W r fd'f Dr vl<'s sayuddy s 4 f* " ~f " Yurn]f v A00 04.cw & l 1""}huuvLifey,epp.pgsy, as = aso o& wM & reu-zum r .n). ~>Izu &

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APPDckX G SIGNIFICANP EVENIS ICG ( i B. Record any changes in the valve lineup, any leaks repaired or other 'fixas' made, and any event which is not ccmsistent with normal operating procedures. t I Recorded Date Time Event By 3/h) O'IS 5 fv"* TW q 03?D F 0 f' M', i g, efG 0330 p' WM C M,;te C ^ a w%- T~ 4 & W i l waQwh.e4/# Cultik. Aes>- C 17 " /S k' 0% h T*r k

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~ <ew..+.s m +e.~ $~ *' * *****'" h '. * "~' #'e #W 15'6 41Ce *W** "'"*** h Rev. 1 10-26-77 7 APPD DIK G SIGNIFICMT EVIN!S IDG 3 N B. Record any ctrages in the valve lineg, any leaks repaired or other ' fixes' made, 'and any event waich is not consistent with normal operating precedures. Recorded Date h Event W (5' d 0 73C S'nshr(t& -l4. M M.t?(c(A .f$A 1 Act.n1.. Ladd e.osr4/Ay. .!. !?. Jya4) du A & pr 4-e 4u '.6.;.5

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We nyw Ac $ % g. u~e2 we /.w ~ve w 4 // g '"R ./ m -d wm y./k. /e45' ./>M'~*<sG M d f )% And ^ Jm m s fg. L 19 S'* ln4. n d.4r.t gajy [yj ". , i s.e pg W~. me a'- s N.00 Dw<re</ yy. vHA f2 % f2,=J't g sAwy ws:q dete sef Ah4

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j ~ m. a _ -, -.. -, -. 4, e,- -, + - ~,.. w is a a o r e ~ w. nev. 1 \\ 10-26-77 APPDDIX G SIGNIFICANT EVENTS IDG ,~. B. Record any changea in the valve lineup, any leaks repaired or other ' fixes' made, ard any event which is not ccrmistent with normal operating procedures. Macorded Date Time Event By $/6 /foo .2v wk /7,G kI6Mer 62-pi gf p p's i@o .w + L n.2 i,, yg 8Off .Cu h k. 16 8 k..lse. P w. 'l T Q'l 4y 71oo W T/L /6 14 a /5 7 A " '/ 6 do al30 Yh 6 15.0 2370 a , 3..g.. ' < 44. 8' oigo h 0 +I ( (2. { < 46.f % *f t(. 2, " %f n' D '~ ~ ~ 5505& p bg $w L p sotr w L k e a k tikfe & mL &df 1 .kulu efotal-109) Ra So RV000f.rw%,y -caujJ2 & 22eo s.n AQhm.r TRR3 It # D r'0 -ef 2Sfo >ce180W BE7~~~ 7~ 7G c.44., d i t r + <- "Y wr rp[gj oo g5Tw Jeu? = D %., OR %. = 77F lLLAG % m tM A-0100 7 Y ? eso ed G & sri av .. ~ 3 a 83 s O e -e ,,.-.r.

M. TSS 15.6.10A Rev. 1 4w,,w.u. w w. m.e. - n m. w w a M r' "w e 9%.e-e 10-2(r-77 '+'" SS * "f APPDDIX G f [$ SIGNIFICANT EVENIS IOG B. Record any chmges in the valve lineup, any leaks repaired or other klfixes' made, and any event which is not consistent with normal operating iErocedures. Recorded Date Time Event r By 3 ${ Oil lb f N - M _/L u.a-M c,n k ;w w RV@b ^ Up Y ' to ga 10 4 # h ._(', & w A p *y 44 40 . cooy n th . wg m. k % f itC7 % 't7/ sA bur cAAA* - ~ AM-uf M 8 w am ok c # osso e.< ice as Rat hap 4 ogif w L4. hd a lo.z-in. g Me pess.d U.r/v3 gS ^ 1.E, SeSd pf4 w' w ~ D '7 ' Ps.A sd 1.- owo .J , e t t" 83 s=-

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Record any changes in the valve lineup, any leaks reg 11 red or other Mfixes' made, and any event which is not consistent with normal operating procedures. Recorded Date Time Event By O 1'O Dwcd( 3o./ M M ('af &- (v pg C93o 4 struA e m 4 ) L 4-e ( = 7,d..y J I g.1 [ j vu wn., 3 oitaa .: n Ma pm ey p yece7. l Al h ' W aX h f f .4cA. l' ' ba' W Ad<A, 4 a at A O (4 C.5 % .ti >( v44c .( D) E4cTrl4sfW% b VC 5/co ve4.< A !2N I 4 t~ d - %rdu1' Lf n y & M at f2crM _kel. jka'ud M &. S +.te LydW^d p .MS < fw Ak puhk- /300 #""d l" " ~ " 'I % 1 7,sj, ) W w L,.Ay41 ya h. 7vg gr a x n v. and.C79 m .t A r. CQ bdd y gSO B3

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' -.~.es.u-v-10-26-77w e v. ' + l APPENDIX G g SIGNIFICMT EVMIS IDG B. Record any changes in the valve lineup, any leaks repaired or other wifixes' made, and any event which is not consistent with normal operating' sirocedures. i 4 Recorded Date Time Event By l U / 3* c g ,( (Mooca y pf0do 3 m se b d Sb a i ya La 7x.a i.sma a .haby &~f. VMWd'Ph< n2r s,d 4 Jf ax y Sk S, 6 di 4 &y fd*9 A Id /, WM 4dy ( i-6 S $ A ( .L. E. fmf,4 y, fa & PAS luaI cAu/ A jaa.d 4 C& sk E ved pik 3230 69. gg LA-< ' & M5w A e A h-Q y . $; fg mo M. <&r L%. e(O p.-epso E~keO & m z0 oc,3r *\\WWW. ,q(4g' 4$ V M L. -tw i ' Y 1 o-, cA w flR "3i ~ ? e 83

TSS 15.6.10A Rev. 1 4 g A -w ee.. w.w.,u.M 1 r %s.:n n.gmm.m.e#me e.- 10-26-77 % w....t APPDCIX G g SIGNIFICMir EVDTIS IOG B. Record any changes in the valve lineup, any leaks repaired or other .', fixes' made, and any event which is not ocnsistent with normal operating procedures. Date Tine Event 49 c23-7gQ ] .)/ u.i g,;g #f ASa Lt7 g oa45' usooo6 p W &&"%) f' o sio o nsooos ( \\ S T 'dW("^^'1 a v W eux. Pe. - 4 Nsk A.aMi f:) (9 o25: 7e 9 -JMcedT~a f-sw. o 500 f%r b. = 8/%, RdR / -Q vc.Qw =%CQ t s/&- q ./,ze = 8 7 % m1 W R. 0550 (w. k MQ W Qwg l'k/A Q 14 d 13 ekJ)m%MW P M a o,X-19 7 P an 7ce,. b.'"i A4 t 0 3 '- A't O*4 f-hemPrimN-S]o.5 $E,, gm !?.od t v is, se.f ~f Ii 7f%<j - ve O%I feorr,s,e' s.Es t 04 kel 9,4, t -cu-a m,s, o $9V'fM'?yt, f>, c,0 9 mee ** 83 i 1

TSS 15.6.10A Rev. 1 .,.h p.2 ,.. ai. w w -c.c,x ~*er .,,.% w.,A mur,.#cu.-~, -+v10-26,77.-ew-w w..* APPDDIX G g r -Q SIGNIFICANT EVDES IDG B. Record any changes in the valve lineup, any leaks repaired or other .' fixes' made, and any event which is not consistent with normal operating procedures. Recorded Date Time Event By 31 Ci 3.e us e ::..] %(,e g-5 C (: - !. [~ s.: O ec. 47 4&lf gB pa? f re n a<< y. n k.hea is L4.u va les. p rq sw.) y g n sa c.a,4e..; ed res,urs.'$%cg></ zene y,n(sse<r ff +c 3 7. h r f t ( yS e./ e / rr na *%*/ t! re + lea Nc nel pj' c l7c. P h Le.., Iie (*J r.,,,,, y > w > -w , 1a psy.. Jf,, , m <r.>w C b c cl /* fv ' * n A hel y rec 17c qu s g,I ch a, ic cc ~ 7. fiv-.t'u<< et SC YJo1 I/f o a k'e tle/ l< fc n.ry ceyoff. b AA O /h e.,cu le,,mFrbsrj a

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== _=% Au y . Qqp : ,.., 9.. _.. c e e,,- - -... _ - - - -. - - -. - - - - - -, - - - - - - - - ~ ~ - ' - - - ' = - ' ~

TSS 15.6.10A Rev. 1

n Wkw.~ w w% w w m *** " "%'* " *~!*===^"***** WN*** * "'

APPENDIX G SIGNIFICANT EVDTIS IDG B. Record any changes in the valve lineup, any leaks repaired or other . fixes' made, and any event which is not consistent with normal operating procedures. i Recorded 1 Date Time Event By yy9'1 oo?D W 6-.u.< Ee&d. DM & M H, '1' K u & chc.ffA@ k ~ ? ku..- N ATV i

    1. R R

c 6 a*9 tto m R IFR ss k i M A. f,& Jef m 2 -a 4 ag'o a i. [ 978 - P'l s

  1. # : %~ d Y c s-rGQ

&Y we a.. A MM d wtaL Aa. A$ q ofif&b M66006. (Su.h%. o(e ~ 4+4D Laaje-wQ4 Jo-) ~~

  • Ni7 $ FS d a/v "W

ty d e JA at df ghf & ^' O e. c. (. a u -. ' & R(9 s& %' M.ah & A % sh/n y so 4

  1. 4 et /s cs 3

Pr.HoJ gp Die W i i 83 cm- . ~ - - ~ ^

.s TSS 15.6.10A 1 Rev. 1 g-1, h +w a-;.. m.we W.%.wW-M*emp. Me*,.,~.w sul0-26-77 AF 4 ~? ' ~ = 7PPDDIX G SIGNIFICWF EVINFS IOG B. Record any changes in the valve lineup, any leaks repaired or other . fixes' made, and any event which is not consistent with nomal operating procedures. R*COfd'd Date Time ht 616 6N ww w n han ato 9 k 45 N ~d .-n. c \\/CT. M A (tH)sT Q . -J3 h (7 \\. c s30 xiaw!P est z< ir e,asc,ax i,sg W/A'W, D'AC, f J #ost czsimp.c z.c,yu pise- ,c a sog ps,, sir

cuo, c4S~ [Q yk 6nts a.4<. &

g4y 4Q. ~ ~~ cAoJ2 Peeg 10, vi va. s 5 50 Tsc b. =- LDE RRfL Q= Ni*FR $eg V c_T g. =3'//g i 6 74L.= S7@ % K-F M99@ efd 4 nu " %A. S A ow %.P & a r </v f C: YW A-83

TSS 15.6.10A Rev. 1 4ifmn ,&= ,uc- % ~mwa= W + L =' = = W *' w :10-2G-TV= % '^ % APPDDIX G SIGNIFICMC EVDFIS IOG B. Record any changes in the valve lineup, any leaks repaired or other . fixes' made, and any event which is not consistent with normal operating

procedures.

Recorded Date Tim Event By ?-!

  • c r ~3

//52 nd c' ' G Y4 j s,9, ~ /- pMV cc eT,.i j 's. Ss* kl<af Y zone y jj,y " 7 E~ + L.W vr +. <&.+ 17

  • in 'so m,b 8' Mo C

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y Yeciyc. tb ag 0 !Jowe w.% % \\ ulde ,h' Q ~miin o go o Sd% gm QA no'd 4f 'l S FP vf 9 Y. 45 E F 7' Vo Pf fo 'd a% ^~0 f NCo ) y !/ Q W W <M 54 4 /r a m 94g idact pncy b z u r. 4/.s o, 0{ VA M*} t [50 ttb1;9.w $81w BoGif Id W .i (. e-** 83 .m.. m. .m -

TSS 15.6.10A Rev.1 ,. 4 ev,3y s -*.ww.m wu. _ _ _. p--m. = - #w.rh. wm.-t x-40-MWe*w - e'* p APPENDIX G ~ [ SIGNIFICANT EVENIS IDG B. Record any changes in the valve lineup, any leaks repaired or other .' fixes' made, and any event which is not consistent with normal operating procedures. Recorded Date Time Event By ]-9il l l.'00 W TooYSw. cc hConUmek GiRiew) Q4skt. h AA h Sfunk ( /< /h ) ys?r LocM ewl P1 e' s$ ss 3s7. se 'x c + nu a fraa,y.5 < >s~< @~. - 1.20 0 cwa' b->Ly(AYC C5 % m A Jud. .1&sc/~ c _1 o Q, I* .. o, & ~ ff mL p& AQ, A'h.Za/ ~ 7 l50 Va keli,.2 e 4 gcgo2r <.y, fdl ( fRT.t je and ge) y M30 [opc/.4e4 dh.~~ & an& gjg ( M i; hoeir. pi}e c %) IS'00 / 2 L.E Vh 1Lv' /kW 'A 't'" prpfofg fdf tuco /& 20 l' M M 7 % Ru2 f n 7Ef' 74: (Hw % e cut.,,,, a e haa'y 100 0 l3, I') E '"ES (E }h N ffCl2(o 1 W y @. /M fut e/*.2) s~ au~da ,n_, im._. ~L L dm'. 83 .~... e-. ' ~ ~ ~

B ~ TSS 15.6.10A %I% T]t '7 Rev. 1 . & A<%.s'sr.A+aY*y m <~.w. w,..,a H.J. un.r-y~nm :.m..u-g26.,,y. w .u...... r r MMOG r-Q SIGNIFICMTf EVDTIS IOG B. Record any changes in the valve lineup, any leaks repaired or other . fixes' made, and any event which is not consistent with rerJnal operating procedures. Date Time Recorded ht BY "p~ o mu l a' ct ;- Ps 3,,.anssm-m 7)g ISWO Sm}: QL 5Sh ho-kodded g y, 3lf 2*" S 3h 2-a mq # y N/* O &-lp& A p,q A a s.c. P p (. SI** k 'N OSh 8' ph twlta ' pM b s. b3 A p@ oucxe ra w rats f r.ur.s y//M con do Ab*(To 0/A*'f! FM - ed Msi f, fr.s' /at rr d'4' '+"-*f'* ? e pirtyr. <o s m e. 'z1o

  • 4& y W8 ?Y31 f fQ

.U" ' ? hIM 21o* fil + ft't. ) Pall A &E m bU h 7-A b O** gg

w. 4 A oi o u

p_6 a 58 w- ~~ n o.* 8,3

TSS 15.6.10A Rev. 1 ..y p >.p s w - w % % w w. w 4 % e; w. %,,,,,10 M w w.~.. APPDCIX G r SIGNIFICANT EVliNIS IOG B. Record any changes in the valve lineup, any leaks repaired or other .. fixes' made, and any event which is not consistent with normal operating procedures. i Date Tine Event NO & OA30 sapw- %x 2 a_c ah. J V& ~k p f ~ ~ M. TQa. ovo azrr Pu-O L ta D lw M A Mw dAld. B01. 'w % w a m 'c e s g g p y (i We //c hWF. {lswSbe?) ^ nif Q " GN,f""' '1 '*" W sW.5;4,/ec/ anhyj and'ht(StN}t<&A' f y'#e /nA &n/. rm c-n,,x /k ll+. f scwrf PE A5Meeg f4 cwn frzwwd sex W o WC pnres a-u:. ,,oux cLM uek &assy g.g4 ec g 83 -. ~ ~ _...

TSS 15.6.10A Rev. 1 _ fgww,.ww,wwcm.':-P^- ^t -,w: Maw * -2 wA*'"""*"*Anm10-26-77#"*

  • i APPENDIX G

,. e SIGNIFICANP EVINIS IOG i ,e B. Record any changes in the valve lineup, any leaks repaired or other ' fixes' made, and any event which is not consistent with nor, mal operating j procedures. ,<ecorded Date Time Event Bv 3/9 c9c' Lected ed c/en,w /.:r 3c a.3/c. O P ^ -it w,ify J.sms e DA pw~j A r&e /'tSh .s'at19 m n.i&C Stw,dir (Wf ] A &j m LA 'sco ~ Eevits4; pa>f As Q [M ffg ( % d4 wi-M fenf) p,f. w -a, sp, a_, pu f PZ l' ' * ~ D re dak a g 1- .m ~ A<*ffh bd a. isso i s t ic. ns M afo yMh MS M h Q io M/0 I t. \\*b (%uuuo' ns/%. t ,-n ce f& 'C f~-kN Ju w a in % -aai. 83, w_.. ...:n : an.-~--------- --v-

~ ~

  • 'ES 15.6.10/s Rev. 1

<.y.- % A % -cw ear-. e v.e'.v w-N. e M m..., w h-w.s= % w,w m.1.,.0.-g ,,w,w,,,,,. APPDOIX G _.g SIGNIFICAVT EVINIS IOG ,q e B. Record any changes in the valve lineup, any leaks repaired or other 'tixes' made, and any event which is not ctnsistent with normal operating procedures. Pacor M Date Time event 9, { dw sdd vu & u'W pg i D W (v 6M<MN m P/ H Y-u:c .at- % ~ A.'S & llC P 3-?b .An,.i"W WW

  • Yk Y 2 w~~m

/ s.: k a ~ & m C-- .vb1Nf y) M-l / ': a ,. n a Hou Vh "W WY f),,tl' /sco & //' N b ZW,; Q verf g /9c cAct. 'I6 /"'sms sM d*f< s,/wt pg n /, c,,a z 7,issae t 3/10/ 8I'9100 ff & PR & fif &.TlU A. Ok LTl59, ateo r>w -us o 17 + A M p Ms W " W/-- go - aa'0 " sp & w) 7 30 & tfu / m.44 PI, Pp utd'Qte %id!L0m a avh A. m,t-A 40 I ijg-83 ......._--~_..,-:;-

s. ~~ TSS 15.6.10A Rev. 1 -d ~.'n.,'., Wym-s-.mnt.*-%>c;. =:::+%<'w% w:.mumi.w o**w-mn..hb?.I rwtw. ~ :~ % APPENDIX G ={ SIGNIFICANT EVINIS IOG r ,- g B. Record any changes in the valve lineup, any leaks repaired or other ' fixes' made, and any event which is not consistent with ncrmal operating 'pcocedures. Recorded Date Time Event By ji//b/f/ 9,9 3D fl , O 8 3 jtAd (icv 4M.W 4 b I J I F I 4 5 If. (w". OW. 9f 3 I Il c i l 5' Fe Mc psi) B o - f.o go o} t. 7eerc.c t 3(, c.h, w cl,.

3. s $ 4..

)?I e4% Ife, b kL w nao c \\', hem M T WE, } fT MS Ib m eglad af% O her4 oogo & H7 Q.. Kh Otto fdh j f* V U o,a a wann s ed e PR N 0 300Q id to IP /> y 6 uw-> s 4f I S Foo lO. .x x Aw h & g. e a t 4.re, p %mek n,% k e=ortPh? /9/r/ % cy10 m 3/II/V/ f'l's A * *l*H YE h * ' O A Y PPi A *, o 'l 3 s. l l 83 l

j Rev. 1 shoe e.,e,-

,c. mew ~ 15"

- r ***he *d**

  • e

" # " ^ "'f' APPDCIX G ,, y SIGNIFICAVT EVDirS IDG ,e ;.* B. Record any changes in the valve lineup, any leaks repaired or ot.her ' fixes' made, and any event which is not consistent with normal operating ' procedures. Recorded Date Time Event By 3/0/8'lo'I'io /0ssn & M 4 +(o Q oss m. (m. & (,,[ q& 04'80 UE

  1. /

f 1W4 P Wh Y g gg u .g L o 7 fo OQ M ff$3M$ W hSOl70 $173 Qf osro L wie sk,w 9 rim,,i.., xm i u. worbny s, MS Itstis. A lt. D (hG fosp starfed +ofremautt. C. fest loan c.t.,,, c)Sh~lo.f G Lt.48 M;th lear,s. L) t/G to.g D Laey fees /h. s nh L L ts t ls e., 9 s.d O J/& ',,u su e d 3~ W lt) 20 I\\A TM Y, g3 L9s PROS $ c laf & Q ~ Wd' y M ~ C0 d.pv (M $7dy lI 5' % 4-44 e.t - 3., w t -M-i m, w i. _ #a. LL g,.e.<.p';\\h ww w~ & A '" h x'H. 7 44 d M # D z y sw c.ux's (f ta h<h 83 i

~ ~~ TSS 15.6.10A Rev. 1 ...-y _..zX. m m -v % % e %.e.Sw o w we =,w -m -.a cu.u+,, w w w..1.D D d h v..r.;.

s...v APPDCIX G

, -{ SIGNIFICWI' EVDf!S IOG r j' B. Record any changes in the valve lineup,'any leaks repaired or other ' fixes' made, and any event which is not censistent with normal operating ' procedures. Date Tine Event By 'b' 9sJ Ra%.novs ;b, 2cra g) _gg sesen - st Jax. e @ s e r % m q,,9 s) cs,,d s zooor n du. 6x'4 dFJ) doo 9sw WMW Q.3 m/ pgs ),ssu~-< ced J24 W b w f&r< 'd .fdd eco A..Aa - pu u,e vAux. ' swr t'* Y' I If see cpAvn sa 2 t8. A MS gg l7fo shded pAaj M.4 #LTT, fle rl.=g e l'at. a m ~ ~ fergse s+.ss 4.s..d.sg.$,,RIT'ermval l'l 3 5 sys+6. Slas Lc. steppga. >)ater ht.,l kelW y A.t.9 019 s ( At-60tS. system oef rt+Jent! to noemel yet. zu H 27" 97,1) .9t Itx

    • 20

/4 H 5 p.t ~ r yn eLT 83

3 5 15._o.10A. Rev. 1 w 4%g.%mwe w -.<. m c i : _i e.w e m *- e'.-*.% M a.'^6 * - "t-v APPDOIX G ^* .E. 0y. SIGNIFICMTT EVDitS IDG \\ B. Record any changes in the valve lineup, any leaks repaired or other . ' fixes' made, and any event which is not censistent with rormal operating procedures. ~ Recorded Date Time Event By 3/k/g)' a36 CAa <S.d) i a.x.R m Act)- sn B8 So Y k cM.G)w gQ "W ca3 & /$ M S& i W *oW.InW \\ 4g 4@

  • 4 W l a M.s e$7 Ax.c Q

o/* D. PP o tu 79 W. t), t, 8 o-3 Ko sr e q s 6'/f L b c.Qan _ @h / t/C. 83 %A 'lAa.Q. d o of20 IBMsek.a p. d n g'(p l. IA i/A-et$~ M Q. 19 $ /9 wq. f i c/55 ) A SM 14 GL R4 M /6 m is @ L A lo 't n Pl ~ (c 't @.L /T % j g) ( l 83 _.1- ~~

Rev. 1 6 2.w.'4:., w 'w r.m w iwe.> m w <='.,: > e,s sk w..w.:ee A,s w w.~.,ye N.W h W ?sr.>,:;.:. c..t1 APPENDIX G ,} SIGNIFICAVI' EVDFIS IOG ? B. Record any changes in the valve lineup, any leaks repaired or other ., ' fixes' made, ard any event which is not ccnsistent with normal operating procedures. 2 Recorded Date.A h g .3M{ osob p w ' gn O n =.oQa u ,a... r eg'O $0k [ SIA 4 30 ced a[lA 030) O Ga -) & W qf W. J)M: & & cake. CD og A ars% n. 9,. Qm osto 8 v_<_.< s - .a h %s_ M 3.90 1 7 A-o345'f e a g qn = aa I y e % m. /C = 1% M 19 = i$ G k. R3 a.. -. ~... -

,r5S 15.6.10A Rev. 1 ,,,.:.,+,,...,.~.=, ma m

-~ < - -+ v ~ + +* '=:~~10,-2 6-7 7,, '* ~' * * '-

APPDCIX G g -{ SIGNIFICWT EVDTIS IDG b B. Record any changes in the valve lineup, any leaks repaired or other ' fixes' made, and any event which is not consistent with normal operating .procedares. Recorded Date. Timl?~ Event By n Fil*/ ),V(M-Q4 = _ e kl. S +A. on. M~= $O ( (k

a. 9 5' S c.FM 4

R. 25 (=H sc

  • O 18%/

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  1. 'fI'1 ep nB

,,... s~. A B C J.A se t. w a "7. B /B ffyp J W bteder restwrte PI' 1 Y a r ej L Veig p s e3 (ea e o-6..ri. ;.7 j M P5-477:e27.5 g a Jp '-il. ,op m 2 t. u r re.. ~. ) 83

- gus u .50n Rev. 1 10-26-7 ,,,,;4 2,.y w ~~ n,,s e-<w+>mso:mM-W '* '"' 'M******* ****L~ ~ - l APPDCIX G 4) SIGNIFICMC D/ DES IDG Record any changes in the valve lineup, any leaks repaired or other B. ' fixes' made, and any event which is not cmsistent with normal operating 'peccedures. Recorded Date Time Event By i 3 ' ;- ! Ik o ,&fiaw c. ,em g? g ?& i G -N.?d6 is/ frae/ lc <f can.- !9 :. g,,

p.. _v,

m: n.~ m si a e p =-: 7 fs, t A ! YC F,.-l <~& / /ry m e< / 6r/ AJ er 2' t:'- .de4: ;J , 5', p.900 Y a @=o y8 & ef0 F.L<y n m &

  • sso

<fo enn 9930 SAu-/& $$$ Vy '6 4 & siis-F&& ^ $R ~ -}$ 4:R. M c4. W aaso s(o ano sL Mt N h

  1. vg.

W% N 3 / 0 8' S.C.F M 's 83 l ~- ~ --- - - = ~ ~ ~ ~ ~ ~ ^ ' J

735 35,5,39,, Rev. 1 .m'so.f &.+,- ws+ ~as y n a w m e w= w = W R m w ~ wn-+ + % > k N N~~ N : v ~ v A APPINDIX G M *g SIGNIFICWI EVINIS IOG B. Record any changes in the va'lve lineup, any leaks repaired or other ' fixes' made, and any event which is not ccnsistent with normal operating " )rocedures. Recorded Date Time Event Bv 3/s n" m G4U LL~.fi>u. sW l A C /*$ A/ tbf L M ~ 4 k. m ) w t B-I' *}l A c ~/. f~ o , 9.:/.L 1 m,,>,, K p %.FJ< dr na.A s aar a nma. w.... 4i 0 + L J A -.6,,L.:. L s eu 4, K Sc<.n Q. war cL L,, f & f m:<e py,ym juk,A _,,.,p_ a.a 7 aux ~ i atmad M yy.p y. wk. ekJ nL #-L 3 >a,m ste,,4 L MJ re jk) 1 ~ } b~e Q m ou 6d W. % D 8 83

...a,. .. s......., Rev. 1 lu-Jb-71 % =* owm 4%m.,o%vu s: %w..armu% e -wsw wnaw-sev. Am %e%,+ 4 APP 32CIX G i \\ n SIGNIFICWT C/INIS IOG ',g. B. Record any changes in the valve lineup, any leans repaired or other t ' fixes' reade, and any event which is not consistent with normal operating procedures. l l Recorded Date Time D/ent W1 7 o j i O w 6 a i l l I L. i 83 a _...

.-,i e e .p Wge ee > 966 eMGh MGhN6 8 W M* OMM*

  • M'O N O h W 4NG &

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9W W 6 O 44 ha, _ rp . Mwd;-i J %BWG $E ~ '** v 4 A *" * f f T 6 4 k L sg s aN s 4 4 m o v w 4 s. 5=9 h, i g-g i w < Q s' 4 N' M' k {E, % * * $ S S $ T k k &y W 4 < s' k k q g Q(I& 1, s o s ~ ss 4o s5. .s y s su N N 4 N Y NN N Y 'V V % % S %h5% g$ l 5k39s 4

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.;~* ] l vg%[o UNITED STATES 4 NUCLEAR REGULATORY COMMISSION ' g g WASHINGTON. D. C. 20555 ' 7. rj NOV 181985 Docket No. 50-295 Dr. Zinovy V. Reytblatt Illinois Institute of Technology (Building E1, Room 208) 10 West 32nd Street Chicago, Illinois 60616 Dear Dr. Reytblatt Your letter of July 31, 1985 makes a number of comments critical of this-Agency's handling of your claims with respect to alleged inadequacies in the containment leak rate tests performed at light water reactor plants in accordance with 10 CFR Part 50, Appendix J. You have pressed your_ claims and allegations with respect to containment leak rate-testing with this Agency over the last several years, and your submittals have received appropriate technical review. This has also been the case with your July 31, 1985. letter. We even held a public meeting with you on October 17, 1985 at the NRC Offices in Glen Ellyn, Illinois, to accommodate your request for a technical discussion of the July 3, 1985 decision (DD-85-10) on your petition, even. though this Agency was not obligated to do so under 10 CFR 2.206. Enclosed is a copy of the verbatim transcript from that public meeting. j i r t The NRC staff has reviewed your letter of July 31, 1985, including referenced correspondence, your collateral correspondence with other staff. members and industry representatives that was related to the public meeting, and the .J transcript of the meeting (including a draft resolution which_you presented), and determined that no new safety issues of significance.have been raised. With respect to the various comments and claims that you raise in your_ correspondence concerning prior actions by this Agency and decisions which i have been made, I view them as opinionated disagreements with the decisions. Consequently, we do not intend to consider this matter further with you. I would like to briefly respond, however, to your discussion, at the meeting, of the Palo Verde, Unit 1 pre-operational integrated leak rate test conducted 'in 1982. You have suggested that-stabilization is a convenient way to eliminate data that would contribute to predicting a higher leak rate, e.g., i, in the presence.of a diurnal temperature cycle. My staff has reviewed the _Palo Verde. Unit 1 test report and finds no evidence or aiurnai eTrects in the pressure and temperature plots. Also, we continue _to maintain that the stabilization period prior to conducting the integrated leak rate test is a vital element in the test procedure, and will be retained.- We note, too, that your slide purports to be a factual representation ~of the Palo Verde, Unit 1 test result, and to the uninitiated, the slide would appear to support your point of view..However, the data from the Palo Verde, Unit 1 test do not follow the curve you constructed.' ff .,,Y, r~~ 3 2g-

.c.

m-y 2 Dr. Reytblatt gV16 W ynmyreviewofthetranscriptofourOctober 17, 1985, meeting I noted dozens of instances where you accused the NRC staff members present, and others with conduct ranging from ignorant statements, up through sham and deceit to fraudulent behavior. Such accusations have been a characteristic of your many pieces of correspondence and meetings with us on this subject. Because of the gravity of these charges we have r.eferred your claims to our Office of Inspector and Auditor for appropriate action. Nevertheless, I repeat what I said in our meeting (TR. pp. 90-91), " confine your remarks to the technical substance." Your habit of impugning peoples character, motives and actions is not scientific, and I consider it inappropriate and unprofessional. Sincerely, ~ Robert M. Bernero, Director Division of Systems Integration

Enclosure:

As stated cc (w/ enclosure): Mr. Dennis L. Farrar, Director of Nuclear Licensing Commonwealth Edison Company e Nuclear Licensing Department Post Office Box 767 Chicago, Illinois 60690 Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Timothy W. Wright III Business and Profresional People for the Public Interest 109 North Dearborn (Suite 1300) Chicago, Illinois 60602 Dr. A. Sklar Illinois Institute of Technology 10 West 32nd Street Chicago, Illinois 60616 Mr. Edward M. Gogol 154 Linden Street Glencoe, Illinois 60022 ) l u-

N44-C q MAY 1 1981 Eoc N t W. 5 % b 8/-0(p Commonwealth Edison Company ATIN: Mr. Cordell Reed Vice President 9 '~'a * * % st 0ffice box 167 ~" m ' ""~ ~ ' 'P- . a w,.,. Chicago, IL 60690 Gentlemen: l This refers to the inspection conducted by Messrs. J. E. Kohler and J. R. Waters of this office on February 28 through April 15, 1981 of 1 activities at Zion Nuclear Power Station authorized by NRC Operating I License No. DPR-39 and No. DPR-48 and to the discussion of our findings with Mr. K. Graesser at the conclusion of the inspection. ~ j t The enclosed copy of our inspection report identifies areas examined during the inspection. Within these areas, the inspection consisted of a selective l examination of procedures and representative records, observations, and interviews with personnel. During this inspection, certain of your activities appeared to be in non-compliance with NRC requirements; as specified in enclosed Appendix A. A written response, submitted under oath or affirmation, is required. In accordance with Sectice 2.790 of the NRC's '%1es of Practice," Part 2, Title 10, Code of Federal Regulations, e espy of this letter, the enclosures, r:- -;-M+: r and your response to this letter will be placed in the NRC's Public-Document d" W - Room, except as follows. If the enclosures contain infonnation that you or your contractors believe to be proprietary, you must apply in writing to this office, within twenty-five days of the date of this letter, to withhold such infonnation from public disclosure. 'Ihe application must include a full statement of the reasons for which the information is considered proprietary, and should be prepared so that proprietary infonnation identified in the appli-cation is contained in an enclosure to the application. Fo/ A 2-c f j f= v+cwn bc 5

G O Commonwealth Edison Company. i We will gladly discuss any questions you have concerning this ~ inspection. Sincerely, . F. Beishman, Acting Director Division of Resident and Project i Inspection

Enclosures:

1. Appendix A, Notice of Violation 2. IE Inspection Reports No. 50-295/81-06 and No. 50-304/81-04 I cc w/ enc 1s: ,h J. S. Abel, Director of Nuclear Licensing K. Graesser, Station Superintendent Central Files Reproduction Unit NRC 20b AEOD Resident Inspector, RIII PDR Iocal PDR NSIC TIC Dean Hansell, Office of Assistant Attorney General 1 RIII RIK RII r Hayes Heidsiman . l

O G-g. ? Appendix A NOTICE OF VIOLATION Consnonwealth Edison Company Docket No. 50-295 As a result of the inspection conducted en February 28, 1981 to April 15, 1981 and in accordance with the Interim Enforcement Policy, 45 FR6754 (October 7,1980), the following violation was identified: Technical Specification 10CFR 50 Appendix J, Section III.A. states in part that "during the period between initiation of the containment in-spection and performance of the Type A test, no repairs or adjustments shall be made so that the containment can be tested in as close to the "as is" condition as possible." Contrary to the above, the licensee reduced the 1A main steam line header g pressure on March 11,1981 at 10:30 PM during the official data taking portion of the 1981 Unit 1 Containment Integrated 14ak Rate Test. (See paragraph 5.C.(2)) This is a Severity Level V violation. Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within twenty-five days of the date of this Notice a written statement or explanation in reply, including for each item of noncompliance; (1) corrective action taken and the results achieved; (2) corrective action to 1e taken to avoid further noncompliance; and (3) the date when full com-pliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation. dated R. F. Heishman, Acting Chief Division of Resident & Project Inspection l / g_%--h-~~~ L(k 6

(..* f$ T i l 1 i U.S. NUCLEAR REGUIATORY CD)tf1NSION OFFICE OF INSPECTION AND ENFORCBENT ~~ i REGION III Report No. 50-295/81-0 6', 50-304/81-04 Docket No. 50 295/304 License No. DPR-39, DPR-48 Licensee: Coannonwealth Edison Company P. O. Box 767 Chicago, IL. 60690 Facility Name: Zion Nuclear Power Station, Units 1 & 2 Inspection At: Zion Site, Zion, IL. Inspection Cond ted: F ruary 28, 1981 to April 15, 1981 sl. p fl l Inspectors: J. E. Kohler /u7 J. R. Waters bNY/ 1 Approved By: W. Hayes, Chi Reactor Projects Section IB 70 I/ // / $j., Inspection Summary Inspection on February 28-April 15. 1981 (Report No. 50-395/81-06: 50-304/81-04) Areas Inspected: Routine unannounced resident inspection of licensee actions on previous items, reactor operations, operator logs, operational safety verification, monthly maintenance observation, monthly surveillance observation, i LER follow-up, Unit 1 Containment Integrated Imak Rate Test (CILRT), radio-active gas releases, containment posting for respiratory protection, containment purging, reactor coolant system level surveillance during refueling, power j operated relief valve block valves, unplanned radioactive releases, calibration of containment high range rad monitors, and boron injection tank leakage. The inspection involved 434 hours onsite by two NRC inspectors including 51 hours i onsite during off-shifts. Results: Of the areas inspected one item of noncompliance (Improper adjustments j during the CILRT, Paragraph 5.C.(2)) was identified. l l -@V960SOTuf, g[ fA Afy-

h; ^ 1. Persons Contacted

  • K. Graesser, Station Superintendent

[

  • G. Plial, Administrative and Support Services Assistant Superintendent
  • E. Fuerst, Unit 1 Operating Engineer
  • J. Gilmore, Unit 2 Operating Engineer
  • P. Kuhner, Quality Assurance Engineer R. Budowle, Assistant Technical Staff Supervisor
  • F. } Lentine, Test Director ILRT A. Ockert, Test Director ILRT Z. Gajic Technical Staff Engineer A. Amoroso, Technical Staff Engineer J. Joosten, Technical Staff Engineer K. Kovar, Technical Staff Engineer
  • R. Rostkowski, Quality Assurance Engineer D. Howard, Rad-Chem Supervisor J. Marianyi, Operating Engineer R. Shannon, ISI Co-ordinator 3

j F. Ost, Health Physics Engineer 4

  • Denotes those present at management exit of April 15, 1981 I

'2. Licensee Actions on Previous Inspection Findings J (closed) Unresolved item (295/80-20-01, 304/80-20-01): Reactor Coolant System Icakage. The licensee has modified the computer program used to measure reactor coolant leakage. The modified program trends pressurizer relief tank level and volume control tank level. 3. Summary of Operations Unit I remained in cold shutdown' the entire repori:ing period.' The cold shutdown condition was extended past the estimated sixty-six day refueling outage which began on January 15, 1981 due to unexpected maintenance modification work required on the Boron Injection Tank j (See Paragraph 14), Boron Injection Tank discharge valves, and 1C reactor coolant pump seals. The containment integrated leak rate test was success-fully completed (See Paragraph 4). Unit 2 The unit operated at power levels up to 93%. Reactor power was limited due to isolation of one of the low pressure feedwater heater strings l because of tube leakage. Three unscheduled reactor shutdowns occurred: t On March 5,1981 the unit tripped from 93% power on low low steam gen-a. 1 erator C level due to an instability which developed in the 25 feed-water pump. Attempts at starting the redundant motor driven feed pump :! l -.. -. -, - - - ~ ~. - -. - _ _ -

G and feeding the steam generators were unsuccessful when the air supply line to the feedwater pump discharge valve broke. The unit returned to power on h rch 6, 1981 b. The unit tripped from 93% power on hrch 11, 1981 on low low steam generator C level due to a trip of a motor control center whichhsupplied power to the 2B feedwater pump oil pump. The motor control center tripped when a contractor working on the Three Mile Island modification for the Technical Support Center drilled into a cable on the turbine floor. The unit returned to power on krch 11, 1981 c. The unit tripped from 93% power on April 3,1981 on low low steam generator C level caused by a sudden decrease in feedwater pump 2B flow. The low feedwater flow condition was caused by a trip of a motor control center which supplies power to the M/A station. When the motor control center tripped several other functions were lost. The motor control center tripped due to an instantaneous trip signal which developed in a 120 volt lighting circuit being worked on for a Three Mile Island modification. The motor control center tripped, before tra local breaker at the 120 volt lighting circuit. 1 The unit returned to power on April 4,1981 4. Containment Integrated Imak Rate Test The second periodic Zion Unit 1 Containment Integrated Leak Rate Test (CILRT) was performed during the period from krch 3,1981 to krch 12, 1981 At the conclusion of 'the Type A portion of the CILRT, a twelve hour period from krch 11,1981 at 3 PM to krch 12,1981, at 3 AM n containment leakage _at a reduced pressure of _2_5PSIGIwas measurea to be .0157 W/0/ day andK0228 W/0/ day at the 95% upper wouuance invet. J Technical Specification 4.10.b imposes the reautrement that the CILRT TypeAtestatreducedpressurenotexceed_J.0729W/0/ day,f10CFR50 ppendix J requi ~- eh-* the Type A leakage" rate not exceed 75% of .0729 W/0/ day or..0547 W/0 Inspector review of the procedure, e events log, 'ihe contain-uu mass plots, and leakage calculation, and instrumentation calibration, as well as independent calculation made by the inspector indicates that all acceptance criteria were met, ce ,0 At the conclusion of the Type A tent. a supplemental test was conduc ,b' by inducing a leak rate equivalent to 2.25SCFM or.0417 W/0/ day his h established acceptance criteria forthe supplemental test of (.0157 + i .0417) +.0182 W/0/ day or (.0393,.0757 W/0/ day). At the conclusion of. the supplemental test the licensee measured.0422 W/0/ day which, therefore, verified the accuracy of the Type A measurement. No items of noncompliance were identified.

0 i j During preliminary portions of the test, before the official twelve hour test of record, containment leakage exceeded the acceptance criteria. l Investigation into the causes of excessive containment leakage resulted in procedure changes and system isolations not previously required by procedure. Each of the procedure changes along with the effect on the test will be discussed in Paragraph 5. The licensee understands that the measured results stated above (.0157/.0228 W/0 day) will have to be adjusted prior to the requirement for containment integrity by specified items in Paragraph 5, such that the combined sum of the measured plus the adjust-ments is less than.0547 W/0/ day. The post test adjustments will be re-ported to the Commission in the required 90 day report and are contained in Paragraph 6 of this report. While all applicable acceptance criteria were met in the official portion of the test, one specific leakane oath develooed as a direct result of the Type A test which reauired inanediate maintenance action. This leakage path developed through seals of both ina*=r==A ane-- =f rinck door shaf ts. ~ Because maintenance needed to be performed on the airlocks in order to successfully complete the Type A test, 10CFR50 Appendix J, Section III. A.(a) classifies the initial attempt at===murinn the lenkm== e=+= = failed test. Ane signtricance of a failure during a Type A test relates g to future testing frequency. In the case of the first periodic failure, the test schedule applicable to subsequent Type A tests shall be reviewed j and approved by the Commission. i Inspector review of past Type A tests prior to the present test revealed repetitive problems with maintaining leak tightness of airlock doors around the shaf t seals. During preliminary planning for the present test, the licensee was urged by the inspector to make every attempt to ensure airlock leak tightness. However, even with increased licensee i. attention, the airlock began leaking sufficient to require inmediata 1:emedial maintenance.. Therefore, the inspector requested the licensee to propose an airlock improvement program. The results of this improvement i program are contained in Paragraph 7, Airlock Improvement Program. ~ l r Since the leakage was corrected during the test and licensee has proposed immediate remedial action to ensure airlock integrity, the as scheduled Type A test frequency is acceptable with no accelerated Type A testing. / j required. Should the next scheduled Unit 1 Type A test fail to meet acceptance criteria, and this failure was directly attributable to the { Type A test, accelerated Type A testing would be required as specified i i 10CFR Appendix J, Section III.6.(b). 5. In Place Type A Test Adjustamnts i ) During performace of the Type A test, measured leakage in excess of that which is allowable was experienced. In order to determine the location of l the leakage and correct it, several procedure changes were made whereby some vented systems were cut and capped, isolation valve seal water was injected, the airlock was sealed with temporary closure devices, the main i ) l l

1 ( ( steam lines and steam generators were pressurized, heat tracing to purge valves was reconnected, and some sample lines were flanged. The. following sections de. scribe the disposition of each of these adjustments:. a. Systems That Were Isolated: (1) Portions of the penetration pressurization (PP) system and instrument air system, were cut and capped in order to positively isolate a possible containment leakage path through the inboard isolation valve and out through PP System. The cap was necessary because the PP system could not be positively isolated from the penetration. Normally a temporary closure device such as a cap would re. quire a post Type A Local Leak Rate Test (LLRI) and an f adjustment to measured Type A results. However, because the PP system is designed as an Engineered Safety Feature (ESF) function supplying sealing air to selected containment penetrations, it was isolated for test measurement purposes only. Consequently, portions of the PP system that were cut and capped for the purposes of the 1981 Type A test do not require post Type A test LLRT adjustments. I (2) Unfinished portions of the Three Mile Island containment wide range pressure modification were found leaking during the Type A test such that isolation by a tesporary closure was required. Since this penetration would always be expected to be in service, temporary closure will require a post Type A LLRT (10CFR50 Appendix J, Section III.A.S.(b)). iThe results of the as lef t penetration leakage along with other test adjustments must be'added to the final measure CILRT leakagt rate of.0157 W/0/ day. The total sum must be less than.0547 W/0/ day. The licensee performed the required LLRI on the Three Mile Island wide range pressure modification with the leakage measured to be 0.0 W/0/ day at a pressure of 48 PSIG. The value was added into the TYPE A results (See Paragraph 6, Adjusted Type A Results). The licensee verified that the equivalent modification on Unit 2 was leak tight. The inspector has no further questions regarding this item and no items of noncompliance were identified. (3) The Containment Pressure and Vacuum Relief Line contains two containment isolation valves 1RV0005 and IRV0006 which were known to leak air prior to the Type A test. The valves could not be made to hold air and the line was flanged closed prior to the CILRT. The station elected to demonstrate positive _ - - ' ~ ~ ~ ~'~~~-~ ~ - -~~' ~ ~ 1

G o isolation of this line by relying on the installed Isolation 1 Valve Seal Water System (IVSW) which supplies high pres.sure t[, Paragraph 5.c.(1). water to valve spaces between redundant isolation valves (See gY y Prior to the need for containment integrity, the li'censee 9 7, must demonstrate that 1RV0005 and 1RV0006 are water tight and that the check valves in the IVSW header are operable. The licensee demonstrated valves 1RV0005 and 1RV0006 were water tight and the associated IVSW check valves were operable prior to the need for containment integrity. The inspector has no further questions rega ding this item and no items of noncompliance were identified. (4) Filters contained in the Unit 1 primary sample systems were blank flanged during trouble shooting portion of the test. These flanges were lef t in place during the entire test. Af ter the Type A portion of the test was concluded, the automatic containment isolation valves associated with'.the sample lines that were flanged were made leak tight. The results of the as-k left local leak rate tests performed were added to the final Type A test results (See Paragraph 6, Adjusted Type A test results). No items of noncompliance were identified and the inspector has no further questions regarding this item. b. Airlock Temporary Closure Both inner and outer airlock doors developed a containment leak at the point where shafts for remote door opening penetrate the airlock doors. The leakage condition was such that a temporary closure was required. Because this leakage resulted directly from the Type A test and was not experienced during the most recent integrated leak rate test performed on the airlock, the leakage condition caused the initial attempt at the Type A test to be classified as a failure consistent with 10CFR50 Appendix J III.A.(a). Since the airlock is designed to be a containment barrier, the temp-orary closure will require a post Type A Integrated Airlock Leakage Test prior to the need for containment integrity performed at full and reduced pressure. The results of the as lef t airlock leakage test at reduced pressure must be added to the final measured CILRT leakage rate of.0157 W/0/ day ailong with other test adjustment additions. The sum total of CILRT measured leakage and adjustments must be less than.0541 W/0/ day. - -. - - - m y_g y-.y iwv--------- w------ --, +, -n

h h i The licensee performed the required integrated airlock leakage test with the leakage measured to be.00006 W/0/ day at a pressure.of 47 PSIG.: The value was added to the Type A results (See Paragraph 8, Adjusted Type A Results). ~ No items of noncompliance were identified. 1 c. Systems Pressurized During Type A Test The licensee has committed to ANSI-45.4, Leakage-Rate Testing of . Containment Structures for Nuclear Reactors. Section 4.6 states in part that,......" lines and vessels containing fluids that are or l may become pressurized should be depressurized and valved off outside the containment to preclude accidental addition of fluids to the con-tainment during the test. i l While the initial station CILRT procedure made provisions for isolating ' pressurized systems outside containment, two procedure changes were implemented during the CILRT which introduced pressurized systems into containment. These procedure changes were enacted while the J station was trouble shooting the initial excessive containment leakage I condition: i Ik (1) Isolation Valve Seal Water System (IVSW) 4 l This system, classified as seal system by 10CFR50 Appendix J. is described in the ESF section of the Final Safety Analysis l Report. As such, isolation valves getting IVSW injection do not require Type C local leak rate tests. Because the IVSW 3 j-utter injection into the valves provided an additional barrier l y 6 cinst containment ' leakage, the licensee committed to perform - [N auditional testing consistent with the In-Service Inspection Program to ensure the check valves in the IVSW headers were N.. operable. N Y The required tests, contained in Technical Staff Surveillance-88, were performed prior to the need for containment integrity and demonstrated check valve operability. The inspector has no further questions regarding this item and no items of noncompliance were identified. (2) _ Pressurized Main Steam Headers and Steam Generators During trouble shooting the excessive containment leakage condition, the steam generators and steam lines were pressurized. This procedure was terminated when a definitive leak was found through the containment purge valves due to inoperable heat tracing (See Paragraph 5 d.) However, the steam generators and lines were j lef t pressurized at various pressures. ! l _._._.-,,.__...--.-.m.,.

G G I During the official data taking portion of the Type A test, from March 11,1981 at 3 PM to March 12,1981 at 3 AM, the licensee 7 reduced the 1A main steam line header pressure on March 11, 1981 at 10:30 PM. While the adjustments to the header pressure did t not appear to have any definitive effect on the containment mass p p. b plot, adjustments made during official testing are in violation of a Y 10CFR50 Appendix J. Specifically 10CFR50 Appendix J Section III.A.a states in part that, "during the period between the initiation of the containment inspection and performance of the Type A test, no repairs or adjustments shall be made so that the containment can ' be tested in as close to the "as is" condition as possible"..This is considered an item of noncompliance of Severity I4 vel V. 4 d. Systems That Were De-energized During final stages of trouble shooting the heat tracing to the purge valves was found to be de-energized. This, in conjunction with the cold outside air, caused the valves to leak. The heat $. tracing was re-energized and the valves were made to seat. hf.h. The licensee has initiated a modification to ensure that the purge V valves are not subjected to cold outside temperatures. The modifica-tion involves constructing an enclosure around the outboard valve. ' I j i No further action needs to be taken other than expeditious completion j of the modification. The inspector has no further questions regarding l this item and no items of noncompliance were identified. 6 Adjusted Type A Test Results The following list summarizes the results of post Type A local leak rate tests and their effect on the Type A test results: I COMPONENT 12AKAGE W/0/ Day Three Mile Island Wide Range Pressure !!odification 0.00 !~ Airlock 0006 } Containment Isolation Valves in the Sample System .000352 ~ j Total coo 041p.## f ta j Final Type A Test Results M j Sum of Total and Final Type A Test g,elCl s.clT d %/41 I The inspector concludes that the adjusted Type A test results meet all acceptance criteria. The inspector has no further questions regarding this i, tem and no items of noncompliance were identified. t ~ 7. . Airlock Improvement Program 1 The airlocks and escape locks and equalizing valves on both Unit 1 l and Unit 2 have a repetitive history of developing leakage during 8-h n.n.~,._,,n .n _.._-yn,--, ,.,,,n,,,.,nn. ,~,_.n,_.e,,._e.,en-.,,.,,,, ,n.,,

-h J + performance of the Type A tests. Because the leakage has caused difficulty during Type A testing and has resulted in the containment leakage exceeding allowable limits, an improvement program has been established and is des-cribed below: ~ Licensee Comitments for Minimizing Personnel 4 and Escape Hatch Imakage a. Increase the local leak rate test duration to one hour allowing forty-five minutes for stabilization. j b. Initiate preventive maintenance schedule for shaf t seals and j equalizing valves: g i I (1) Rebuild all equalizing valves (two personnel and twoh MMH escape) each refueling outage, gu (2) Replace all shaft seals every other refueling outage. 1 (3) Torque the packing on shaft seals each refueling outage. c. The local leak rate test should be performed following any maintenance on the hatches as described under item (b). d. Evaluate new hatch designs or seal designs. The inspector has no further questions regarding this item and no itemq of noncompliance were identified. i ) 8. Type B and C Leakage Results ~ 4 The results of the licensee's Type B and C leakage testing indicates 1 that the sum of the leakage meets the acceptance criteria specified by Technical Specifications and 10CFR50 Appendix J. f No items of noncompliance were identiftad. 9. Power Operated Relief Valve Block Valves (P"1V) The resident inspectors received a request for information from the regional office concerning Westinghouse FORY block valves with the designation 3GM-88 These valves were found not to be capable of closing against full system pressure. Zion Station has no Westinghouse 3CH-88 block valves installed or in the warehouse. The inspector has no further questions regarding this item. l t

  • f' i

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10. _ Allowable Duration of Containannt Purains

~ The resident inspectors c1:.rified a requirement regarding the allowable amount of time annually that either Unit 1 or Unit 2 can be purged using 48 inch purge valves. The licensee was under the impression that the NRC 1 had restricted purging on each unit to a anximum of ninety hours yearly. 1 The resident inspector discussed the criteria for purging with the NRC operating project annager. It was determined that the ninety hour purging restriction was no longer in effect. The only current restrictions applicable to Zion Generating Station are contained in a letter dated January 15, 1931 from S. Varga, Chief Operating Reactors Branch #1, Nuclear Regulatory Commission to J. S. Abel, Director of Nuclear Licensing, Commonwealth Edison Company.

11. Alpha Concentration in Excess of 10CFR Appendix B On March 30,1981 at 0900 a Zion Station Radiation Protection Technician l

telephoned the Region III office stating that alpha activity in Unit 1 ~ containment was in excess of 10CFR50 Appendix B limit of 2.0xE-12 micro-curies per cubic centimeter. He alleged that the licenses was reluctant I to post the containment airborne requiring half ansks. He indicated that I, g only af ter continual prodding on his part did station management post the containment airborne. The inspector investigated the circumstances involved and interviewed the station health physicist and chemist. According to the station annagement, the 0900 containment air sample on krch 29, 1981 (the previous day) showed elevated (6.85xE-12 micro-curies per cubic centimeter) alpha in excess of 10CFR Part 20 Appendix B. Station Procedure RP-1310-11 " Posting Areas for Airborne Contamination", requires posting for k .espiratory protection when alpha activity is above 2xE-12 micro-curies per cubic centimeter after twenty-four hours decay. After twenty-four hours decay, the previous day's sample measured 2.5xE-12 micro-curies ) per cubic centimeter at about 0900 on March 30, 1981. The licensee re-j sampled for alpha and had a annagement meeting. At 0915 to 0920 station annagement posted the containannt airborne. The twenty-minute delay in posting the containment airborne was caused by the annagement aneting and the resample.1 (The resample was counted for five minutes and showed elevated alpha concentration). It was determined that a resample was necessary because of the low counting efficiency'for alpha ' radiation ex-perienced by the licensee's equipment (4%). The inspector verified through shift logs that containment purging was terminated at 1000 on March 30, 1981. The licensee investigated the cause of the low counting efficiency on. March 30, 1981 and attributed it to improper sample preparation resulting in an ultra conservative calibration (counting equipment indicating higher concentration than actually existed). A porous fiber filter had been -10

i (.- Q used as a base for the sample. This caused the alpha radiation to be absorbed in the filter rather than in the cour. ting medium. Af ter checking with the mandacturer, a glass fiber filter base was used and the instrument recalibrated to an efficiency of 10%. This resulted in the alpha airborne concentrationsireturning to below 10CFR50 Appendix B criteria and the contain-ment sirborne posting was removed. After the containment postinE for airborne on March 30, 1981, several workers who were in the containment complained that they were not notified of the airborne condition until they exited. The individuals requested and received additional counting for internal contamination. No evide.cce 6 of internal contamination was found. No items of noncompliance were identified.

12. 0-R-14 Alarm of March 18, 1981,

\\ At 0831 on March 18, 1981 a high' radiation alarm was received on monitor 0-R-14. (auxiliary building vent ' gaseous monitor). Monitor 1RT-PR-25, which. also monitors the auxiliary building vent gaseous activity showed a, concomitant increase. Investigation by the licensee could produce no apparent cause for the alarm. A second alarm on 0-R-14 was received at approximately I 1400 the same day and operating personnel were able to correlate lthis alarm with a venting operation on a temporary differential pressure cell installed on the volume control tank. Research indicated that the venting operation had also been performed at about. 0830 and was the probable cause of the first alarm. Calculations by the licensee showed that both releases were only a small perce.ntage of the' maximum allowed by technical specifications. NRC headquarters in Bethesda was notified by Anargency Notification System i of both relearer. No items of noncompliance were identified.

13. Clarification of High_ Range Radiation Monitor Calibration Requirements

~ In response to licensee inquiries, the inspector determined, through conversation with the licensing project manager, that electrenic calibration J is acceptable la fulfilling the requiremente of Table II F.1-3 of Nureg-0737 for the range of 10 to 103 R/hr. No items of noncompliar.ce were identified.

14. Boron Injection Tank Imakage (BIT) Unit 1 On March 2,1961 while attempting to correct what was thought to be boron

/ injection tank manway seat leakage,. personnel discovered leakage from a 3/8 inch diameter hole drilled in the carbon steel pressure vessel per-pendicular to the manway centerline. Investigation revealed this to be a test hole penetrating through the carbon steel up to the stainless steel sleeve or liner on the inside of the manway opening. The hole is used for liner testing during tank fabrication. 14akage out this test hole indicated a breach.of the stainless steel liner. Drawings showed similar test holes on the BIT inlet and outlet nonles. These were checked and found to be l .. ~

l O 6 1eaking also. Concern over the effect of boric acid on the. carbon steel pre =sure vessel and the desire to evaluate the mechanism of the, liner failure led to the licensee's decision to replace the BIT. An gli stainless 1 steel vessel was found to be available from the Braidwood Station. The BIT replacement was complete by April 2,1981, and resulted in a twenty-four l ~ day extension of the refueling outage. ) The old BIT was dissected for examination. Pentrations were found in the cylindrical manway liner wall and in the weld joining the liner to the aanway seating surface. The most severe area of degradation of the carbon steel occurred underneath the penetration in the liner wall. Here the' boric acid had corroded a crater approximately 1 1/2 inches in diameter by 5/16 inch deep in the carbon steel. Channels from this area and from the weld penetration lead to the test hole. Preliminary results from samples sent to Westinghouse indicate intergranular corrosion attack in the area of. the liner penetration and transgranular corrosion cracking in the area of the weld penetration. Possible causes for these types of attack are sensitization of the stainless steel during heat treatment of the vessel and impurities in borated water. As documented in LER 50/295/81-08 detailed investigations are still in progress and the licensee will update the LER when the final report is - g ' received. On April 3,1981, the test holes on the Unit 2 BIT were inspected and no evidence of leakage was found. At this time the licensee plans no further action on Unit 2 BIT until the scheduled refueling outage in September of 1981. Submittal of the final report on the results of Unit 1 BIT examination is designated as Open Item 50-295/81-06-01.

15. _ Operation of the Reactor Coolant System (RCS)

During the Unit I refueling outage a differential pressure detector was connected to RCS piping to provide remote RCS water level indication. The signal from this differential pressure cell is fed to a pen recorder ~ in the control board, and to the meter which normally indicates uncom-pensated pressurizer level. The calibration is such that the lower and of the meter and recorder scale corresponds to a level slightly below the nozzle centerline. A prerequisite of the containment integrated leak rate test requires that the RCS be filled to at least 80% of pressurizer level. Operators established this level using the uncompensated pressur-izer level meter not realizing that it was connected to the temporary RCS d/w cell. This misconception existed during at least two shif ts. The error was discovered and corrected prior to the start of the leak rate test. The procedure for installation of the temporary level indi-esting system has been modified to require that caution stickers be placed on the uncompensated pressurizer level meter noting that it indicates RCS level. l l l

l (.) h o 1 No items of noncompliance were identified. l

16. Review of Plant Operations - Startup

~ ~ The inspector reviewed the licensee's administrative controls governing. Unit I return to operation from the refueling outage. The prerequisite o list 00P-O was reviewed for adequacy and for completion prior to leaving cold shutdown and hot shutdown. Contain.nent tours were performed to verify cleanliness and general system status. The inspector actanded the onsite review meetings for both hot shutdown and start-up, in which all outstanding items were evaluated for relevance to the particular event. Compliance with various technical specification requirements for start-up was verified by the inspector. Portions of the prestart-up surveillance testing and approach to criticality were witnessed and reviewed for ad-herence to procedures and technical specifications. No items of noncompliance were identified.

17. Operational Safety verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the months g

-of March and April,1981 The inspector verified the operability of i selected emergency systems, reviewed tagout records and verified proper e return to service of affected components. Tours of the auxiliary building and turbine building and Unit I containment were conducted to observe plant equipment conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance. The inspector by obsef-vation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan. The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the months of February and April, the inspector walked down the accessible portions of the containment spray systems to verify operability. The inspector also witnessed portions of the radioactive waste system controls associated with the shipment of spent resins from the Unit I deborating demineralizer. These reviews and observations were conducted to verify'that facility operations were in conformance with the requirements established under j technical specifications, 10 CFR, and administrative procedures.

18. Monthly Maintenance observation Station maintenance activities of safety related systetas and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry

{ codes or standards and in conformance with technical specifications. l

) C The following items were considered during this review: The limiting conditions for operation were met while components or systems we.re removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities vara accomplished by qualified personnel; parts and materials used were properly certified; radiolo-gical controls were implemented; and, fire prevention controls were { implemented. l Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performance. The following maintenance activities were observed / reviewed: 3 Unit 1: Boron Injection Tank Unit 1: Boron Injection Tank Discharge Valves Unit 1: Containment Wide Range Pressure Unit 2: Containment Wide Range Pressure Unit 1: IC Reactor Coolant Pump Unit 1: Reactor Vessel 14 vel Indication i Following completion of maintenance on the IC Reactor Coolant Pump Seals, the inspector verified that it had been returned to service properly. No items of noncompliance were identified.

19. _ Monthly Surveillance Observation l

The inspector observed the following required surveillance testing: O Diesel Generator Test, Boron Injection Tank Inlet and Outlet Valve Imak Test, Volume Control Tank Level Instruments Test, Diesel Generator Tests on 2A and 2B Units, Hot Rod Drop Tests, RTD Cross Check Tests, and verified that testing was performed in accordance with adequate proce-dures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel. No items of noncompliance were identified.

20. Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action.--

- - =.. - - -

3e r was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specifications: MR 10 Unit 1 4 80-20 Update on cause of RTD Spiking Low 81-04 RHR Recirculation Valve Micro Switch Out of Tolera'nce 81-05 18 Recombiners Found Not Interchangeable 9 81-06 Fire Sump Rad Monitor ORT-PR-25 Failure 81-07 Failure to Perform 50.59 Review i ~ 81-08 BIT Liner I4akage 81-09 Missed Sample on Fire Sump l MR NO. Unit 2 81-02 Purge Monitor Reading Iow 81-03 Faulty Microswitch on RHR Recirculation Valve Regarding M R 50-295/81-08, see Paragraph 14 for details. Regarding M R 50-295/81-09, this is considered a licensee identified item of noncompliance in which no citation is issued. 1 I I No items of noncompliance were identified.

21. Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. One unresolved item was disclosed during this inspection.
22. Exit Interview

{ i The inspector met with licensee representatives (denoted in Paragraph 1) throughout the month and at the conclusion of the inspection on April 15, 1981 and sunnarized the scope and findings of the inspection activities. The licensee acknowledged the inspector's comments. l. . _. _ _ _.. - ~., _ _. _., _ _ _ _

!.- N. i ~ ? Commonwealth Edison Zion Generating Station E PRTNCIPAT, STAFF aitch Blvd. & Lake Michigan Zioc illinois 60099 3IR i SL1S : Telep, one 312/746-2084 -D/D PAO A/F gto y b.&PI ,go Juna 19, 1981 bE'&OU P File Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Please find enclosed one (1) copy of the Zion Unit 1 Reactor Containment Building Integrated Leak Rate Test Report mi t n,$@ *. 2 / nsD f K. L. Graesser p Superintendent Zion Station fol7 f,@6 Il -$1CL.. .'d-Fo/ A -f 4 -24 "JUN 2 9 198P l A/6

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... ; :.r. c.io n-Integrated Leak Rate Test of Zion's Unit 1 Reactor Containment Building Written by:

,/ (e) /ibc 21.1 Gajic / 1 'Edgineer Tjiich. Staf j + g Approved Sr: /, m {/ JihthoTI Tech. T iY. "Slies~i Staff Supervisor i Date: April 24, 1981 1

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- h (, 4 Table of Contents ~ Page Abstract 1 Procedure 2 Discussion of Results 4 Log of Significant Events 5 Computation of Containment Leak Rate 11 verification Test calculations 12 k ~ ~ Figure of Merit Calculations 13 Containment Mass Change Due to IW Injection 15 Type B and Type C Leak Rate Results 1978-1981 17 Post ILRT Leak Rates of Repaired Items 20 Sensor Locations 21 ~ Appendicies: A. ~ Graphical Presentation of the Results 23 B. Sensor Calibration Data 34-9.* _-,._.-...r___,_..,_.,_m. -__.,,,,-v,

(? (@ List of Graphs and Figures Fig. A Instrumentation Arrangement Fig.'1 Sensor Locations Above 617' Elevation Fig. 2 Sensor Locations Below 617' Elevation Graph 1 % Leakrate v/s Dataset Graph 2 Con't of Graph 1 Graph 3 . Containment Dry Air Mass v/s Dataset Graph 4 Con't of Graph 3 Gra'h 5 Containment Dry Air Pressure v/s Dataset g p Graph 6 Con't of Graph 5 Graph 7 Average Containment Temperature v/s Dataset Graph 8 Con't of Graph 7 Graph 9 % Imposed Leakrate v/s Dataset Graph 10 Containment Dry Air Mass for Imposed Test i w e 4


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{' y Ahstract The following report presents the results of the Inte-grated Leak Rate Test of Zion's Unit 1 Reactor Containment Building. The test was carried out in accordance with 10 CFR 50 Appendix J and the Zion Technical Specifications between the 2nd and 13th of March, 1981. The calculated leak rate (0.01584/ day) and the upper confi-dence limit (0.02354/ day) over the 13 hour test period are well within the 0.05471/ day criterion. The supplemental verification test finding, likewise, is within the acceptance range. There-fore, this test has succeeded in demonstrating leak tight char-acteristics of the subject containment structure. + g O e S e m -m w -e-ng >,:---ee-r----

g g 2' Procedure The absolute method'for measuring the containment leak rata was exercised on this test. Dry air mass in the contain-menu was measured as a function of time by the use of 2 pre-cision pressure gauges, 10 deweells to correct for the water vapor pressure and 29 resistance temperature detectors. The dewcell and RTD sensors were placed inside the containment volume according to fig.1 and fig. 2. Pressure detectors remained external to the containment with its sensing lines only penetrating into the containment. The containment was pressurized to approximately 42 psia. The data for all three parameters was transferred from the data aquisition system to an Apple II computer on a 10 minute interv-al basis. Here, this raw data was processed and values of containment mass, leak rate, and upper confidence limit printed t ..out: The test was performed over a 13 hour period. Following the completion of the leak rate test, a supple-mental test was performed to verify the accuracy of our testing method. A known leak was imposed and the combined leak rate measured as in the preceding section. This part of the test was terminated as soon as the error fell inside the 25% band. W e 9 .e 4 .---,,-..-.,--.n,, -,--,,m--.. ,-...---.,,.,,--,---,--,-,,-...,---,,-y#

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~ Penetrations thru Inner Personnel Lock Door Data Acquisition System Apple II Printer Computer i (~h 1 I Multiplexer ,r J l f*mm/ Lu Leak ,,/ LVFM-1 Verification / j f Flowmeter r Pressure Standard (Backup for P1 & P2) O RTD's' Dewcells Inside Outside Containment Containment i. Fig. A - Instrumentation Arrangement

~ G Discussion of Results a ~ Going into the ILRT, several alternatives to the original' line-up had been approved in an effort to eliminate excessive leakage from the containment. These changes were captured in the I.og of Significant Events (pg's 5 thru 10). Looking at the leak rate plots (graphs 1 & 2) one notices data scatter early into the test. Such behavior is usual and can simply be attributed to the statistical characteristics. Approximately half way into the test (data set 293), enough data had been accumulated to overide the early volatility and give truer indication af the leak rate. This same trend was observed during the imposed portion of the test (graph 9). Nearly 13 hours into the test, a steady leak rate of 0.0158%/ day was achieved. Based on this result and the fact that the con-tainment had been pressurized above 25 psig for longer than 24 hours, the test was concluded at that point. i ( ,'~ failed or assumed alternate line-up were locally air tested ~ Following the completion of the ILRT, the areas which at 25 psig or above. The results are summarized on page 19 of this report. The total leak rate, including the post ILRT contributions, is well below the 0.0547t/ day criterion. This report also presents analytical look at the IW affect on the computed leak rate (pgs. 15 & 16). As was shown there, the volume of water which entered the containment was relatively small such that the air volume change was insignificant. In turn, the mass change over the injection period was negligable encouraging one to conclude that the IW effect as a whole was insignificant. ~During the course of events leading to the start of the ILRT, a number of sensors were ruled out due to their erratic responses. Included in that number were 5 deweells,1 RTD and 1 bourdon tube pressure sensor._ Tne figure of merit analysis -- Ipage 13), nowever, snowec enat the combined error due to instru-mentation is far less~ than the 0.25 LT upper limit. This indi-cates high confidence in the leak rate results despite the re-duced number cf sensors. Therefore, the results of this Integrated Leak Rate Test are reliable and serve to point out the superb condition of Zion's Unit 1 Containment Building. } m ,_-,--..y, ...,-_-,~._-,,.,,..-~,...w,.,-,- ---~yy.-,,,,.3y,.,y,,_ ww.- .,.y,,,ww,ww-,~

b {.g 5 Log of Significant Events Monday, 3-2-81 T 0415 Compressors started; began pressurization of I U-l Containment-p 1530 Found shaft seal leaking at inner personnel door. 1600 Decided to equalize personnel lock with containment and use outer door as barrier. 1700 Found instrument cable penetration leaking above outer personnel lock doo'. r { W% 1730 Compressors stopped; containent pressure at%42 psia. Closed RV0005 & RV0006; vented RV line. 1750 Filled pressurizer to 80%. 1830 RV blank flange in place. Test started. Tuesday, 3-3-81 0030 Computer showed increase in leakrate. Leak could not be found at this time. 0230 Found a small leak on the DAS channel selector cable (between wire and outer sheath). 0300 Instrument Mechanics stopped the leak on instrument cable. 3( 0600 Found a number of leaks around the fittings on PT-CS50 and PT-CS51 (New Containment Pressure Transmitters). fe"[') - 0610 s' -s Fixed leaks on PT-CS50 & 51. 0800 Found that pressurizer cold cal level channel was not a valid indication of Pzr. level. Decided to fill Pzr. to 2 90% on hot cal channel. T 0830 Found personnel airlock inner door shaft seal at ) a C* outer door leaking. Adjusted handwheel slightly {% and reduced leakage. b 1144 Terminated Pzr. level increase; level = 88% on hot .y +- cal channel. Closed OWD0064 and U-2 WD17A&3 to isolate cotential $~ leakage path rough U-l WD17A&B., E h a.lua& h mA L.u. u al OM V 9

() Q Computer still shows leaks. ] /' Found a small leak on vent line between RV0005 # v f - 2310 and RV0006; stopped leak.~- f YV-p o Wednesday, 3-4-81 e_ y 0010 volumetrics Rep. checked the DAS; Everything'OK. Operating Dept. informed that the suction and dis-charge manual valves on IB & 1C Containment Spray Pumps were isolated.. Data indicated that mass was somewhat stabilizing around this time. 0515 Operating Dept. began isolating the manual Suction and discharge valves on 1A Containment Spray Pump. -*0530 Noticed drastic drop in leakrate between 0400 and 0430. Leakrate below acceptance limit. 06,00 g Suction and discharge valves on lA CS Pump isolated. + 0700 Leakrate increased above the limit. 1120 Raised VCT pressure to 2: 30 psig, j 1200 PP vents, PP 105-108 closed CPartial clear of 0051. 1330 Ran charging pump on recire. BIT pressurized to ^' 300 psig. 1500 Met to discuss use of IW to identify leaks'. - 1540 Setting up to inject IW between DT valves suspected of leaking. i p Wo =- 1600 Observed pressure build-up on PP-28, 29. m,, A Investigating. O wa-it-

  • A

- 1800 Injected IW between DTS170-DTLCV 1003, DT9159A&B and i DT9160A&B. 2045 Mass stabilizing. p 2250 Injected IW between WD17A&B.- M OW-2320 PCV-NT09 sensing line found leaking. Leakstopped.[ k (PP

  • 76 % sq h,

Thursday, 3-5-91 0200 Leakrate increased. Started lining up the res't of ( = IW system. Gave go to drain BIT. _ g 0320 Found lower shaft seal en personnel lock leak-ing excessivelly. ~~ i

9 0330 Tried to depressurize the Personnel Lock volume-but failed when the inside equalizing valves stuck open..Could not get in to fix the shaft seal. 0730 Reinitialized leakrate calculations at data set 332. Leakrate 0.0354/ day. 1000 Leakrate increasing. 1045 Decided to fix leak on lower airlock shaft. 1245 Leak on airlock shaft fixed. I r 1600 Discovered problem with PI-2 pressure sensor. Set P2 = P1 starting with ' data set 406. 1700 Reinitialized at data set 39,0. i Friday, 3-6-81 I 4 g - 0710 Dewcell on channel 30 locked tu~t (appeared to be stuck on one value). 2 - 0830 Installed a pipe cap on RV0007. Looking for leaks. -~ 1300 Observed pressure decrease on PI-PP29 (decreased about 0.5 psig in 1 hr.). Continuing to investigate. Opened PR0002 and PR0003 one at a time to look for possible leakage path. No leakage observed. 1325 Began draining water out of B main steam line in order to use pressure gauge to look for possible leakage into the steam line. ~ 2370 Pacmutad operating department to vent the contain-ment Sump Valve Housings. Saturday, 3-7-81 _D030 Fixed leak around the shaft on personnel hatch. 0310 Opened MS0006 and pressurized *the line to 24 psig. Pressure was still holding after 20 min. 1 0850 PP air cut-in to PR solenoid valves. Pressure is set at 29.7 psig. 1615 Performed the test on instrument air isolation' valves. N Found that IA01A leaks. 2

( ( 8* 1635 Experienced sharp mass drop. Found that operating unisolated 1B CS pump. 1650 1B CS pump re-isolated. 2100 Blank flanges installed on PR Filters. 2130 Air tested 1B CS Pump header isolation valves. No leaks. i 2210 Found PI-1 digital counter not tracking. Reset the counter. Unlocked PI-2 at data set 231. 2345 Channel select cable for the DAS was pinched and leaked slightly. IM's fixed the leak. e Sunday, 3-8-81 0115 Closed MS0006 (Back to normal line-up on this valve). 0254 N2 cut into U-l containment to accumulators. ip g tauwamulator valves are closed). 0415 Closed PR0006, 10, 14 & 18. p SqP 0600 PP Flow to Zone 4 is pegged high. 0730 Isolated PP Zone 4. Bled down very fast and built up at a rate of 17t in 30 min. 1145 Locked out PI-l at data set 307. Counter was not tracking for a short time. 1410 -alEnd_in IW to RC8025 & 26 (PRT to gas analyser). i l Verified IW valved in to DT9160A&B. 1630 Closed PP0126,127,128,129 (Vents on Electrical Penetration Headers). to look for pressure build-up. None observed after 1 hr. 2200 Locked out Deweell on-Jchannel 739., 2400 Blanked off Ril & R12, PR12A&B monitors. Monday, 3-9-81 0030 Capped IA line 0520 Locked out channel 436 0710 Setting up to pressurize main steam lines with service air. t 1 ,.---m .c,.-..en,----.. ,..,..,,,,..,,s.,.,.~,.__..-,,-,_m .,.w...,,.,,.my,,,,,...--.--,_,_%_

g. c 1730 Reset data set to 1. Put PI-2 back in. 1830 IB & IC MS lines pressurized to 25 psig. 2010 1C MS line down to 13 psig. Repressurized to 25 psig. 2150 Cut in PP to zone 4 headers. Flow pegged high. Could not find the leakage path. Tuesday, 3-10-81 1 ~ 0030 Isolated PP to Zone 4 and vented the headers. 0245 Pressure in 1C MS line increased to 50 psig. 0545 Took a helium sample from PP Zone 4. Pegged the He detector. ~ 1200 Attempting to locate and isolate leak on PP Zone 4. g 1220 Started pressurizing 1A & 1D MS lines. 1500 Capped PP line to IW in vertica'l pipe chase. 2100 Cut and capped PP line to PR and IA valves. Wednesday, 3-11-81 0135 Closed IVC 8382A (Seal water filter outlet) 0430 Switched from #2 Spent Fuel pump to il so as to increase the pressure against valve 1SF0010. g g4 0530 Connected a pressure gage to seal water' injection M line. Pressure at 6.5 psig. 1130 Found a major leak on Containment Purge Supply Valve (outside).. g 3 1313 Purge valve & shaft seal Fixed at data set b N Started the normal ILRT. t f 2320 Started bleeding down 1C MS'line. lA MS line is at 20 psig. Thursday, 3-12-81 0040 Started bleeding down 1B MS line. 0100 Opened PP 0126, 127, 128 & 129. No pressure. Varified SI 8965A&B closed. Unisolated IVC 8396A (Seal water teturn filter). i \\ l ,-.-n ,.. - -..., _,.,,,.,...,,,, ~. -,, -,,,..,..,,~+.,-v.,

(,, (;i. y_ 'd ~ 0155 1A steam line at 24 psig [ ~' 1B steam line at 26 psig 1C steam line at 21 psig 1D steam line at 19 psig 0300 Completed normal ILRT at data set #326. ASL - 0.0158%/ day UCL = 0.0228%/ day 5 0301 Opened SOV-PR 25B & 26B to pull a sample prior to the Imposed Leak Test. l ~ Began induced leakrate test. c,/ day' ) 0429 l I Rotometer reading 2.25 scfh e 0.0418% i Data set #334 is the starting' point.- 1200 EUT ump stopped. 9 1400 Re-initialized imposed leak calculations from 369. + /aia/2. ( 1700 Re-initialized from 367. 46 'Y1 IO!L ( (f 1745 Terminated imposed leak test at data set 405. 2030 Stroked. RER Pump B sump valves (,,'3'5 A #

  • p.

2115 Finished stroking RER 1A sump valves. w @,* 2230 Started Containment Blowdown g Fridav, 3-13-81 0700 Completed Blowdown of U-l Containment. I 3 5(, M S e __m-- .--g v.,--,,,.,.,-,.---m,-m-,,,,,--r -,w,---m- -3 ,.-.m,-- .-,,.._,-.,,---,.y,. - i, n,mw. .-,--,,,m-, ,r-.- .,-,---www

C Ce 11 COPUTATION OF CONTAIPNENT LEAK RATE Least Souare Leak Rate L = (-A)(2400)/B A = N I (ti)(Wi) - (Iti)(IWi) N I (ti ) - (I ti)2 2 ~ 8 = I Wi - A I ti N Wi = (29.97)(I A4)(P1)(V) (1545.33)(Ti + 459.69) Pi = PT1 - Pyi where L = calculated leak rate in weight X/ day + I A = least souare fit of mass change slope (lbs/hr) 8 = calculated containment dry air mass at time = 0 (lbs) Wi = contairvnent dry air mass at 1" data set (lbs) i Pi = average containment dry air pressure at i* data set (psia) PTi = average absolute containment pressure at 1" data set (psia) Pyi = average containment vapor pressure at 1" data set (psia) t1 = test duration at the 1" data set (hr) N = number of data sets Upoer Confidence Limit UCL = L + e(TE)(2400) 8 1/2 f(NI(Wi)2_(gwi)2 1 A2 a= (N-2) \\ NI(ti)2 - (Iti)2 TE = 1.647 + 1.455 + 1.976 (N-2) (N-2)2 where UCL = 95X upper confidence limit (X/ day) = stancard deviation of least souares sicpe (lbs/hr) e TE = value_ of the single-sided T-oistribution function with 2 degrees ~. of freedcm -) i

6 6 12

  • VERIFICATION TEST CALCLLATIONS Acceotance Criteria:

(100) (Lo-L)-L < 25% o 'T ~

where, L = least souare containment leak rate 1

La = imposed leak rate Le = least souare combined leak rate of the containment and the imposed leak Ly = maximum allowable leak rate of the containment at 25 psig \\L = 0.0158%/ day L = 0.07294/ day ( T Lo = 2.25 scfm = 0.0418%/ day - Q = 0.04225/ day (100) (0.0A22 - 0.0418) - 0.0158 = 21.12% 0.0729 21.12% < 25% e /,~'

13 FIG.RE OF MERIT CALOJLATIONS 2 x (10 ) 2 ( )2 +2 ,)2+( )2 1/2 FON = (Ept)2 (Cpt)2 1/2 ept = + /# of sensors (E y)2 (ggy)2 1/2 epv = g (e or sensors t)2 (C )2 in (E + et t

  1. of sensors where, > FOM = figure of merit i

1 ~~ e = measurement of change of parameter error E = sensor repeatability error readout error C = h a test duration 13 hours = P = containment absolute total pressure = 42.16 Asia ( T = containment average dry bulb temperature = 523.74* R 1. Total Pressure

  1. of sensors = 1 Ept = 0.001 Cpt = 0.000 (0.001) 2 (0.000)2 1/2 ept 0.001

= + = /1 2. Vaoor Pressure

  1. of sensors 5

= Ey 0.00232 = p 0.000056 Cy = p (0.00232)2 (0.000056)2 1/2 = 0.0010378 epy = + /5 ,----__---,-,m-,-wm ..,-,,.._...,,,,,,-..,_y ..-.,~-,w., s, -m,-, ,,ep

G u 3. Temoerature

  1. of sensors = 28 Et = 0.006

= 0.01 Et (0.006)2 (0.01)2 1/2 et + = 0.0022039 = 2 therefore, FON = 24 x (10 ) 2 (0.001) 2 + 2 (0.0010379)2 + U E 42.16 2 (0.0022039 )2 1/2 0.00899 = i 532.74 FOM < 0.25LT (0.25LT = 0.01823) r 9 t i i ~ 9

( g ? 15 4 Containment Mass Change Due to IW Injection a Assumptions: 1. All IW water used went into the containment. 2. Starting pressure is 42.0 psia (P )1 3. Containment temperature at 64 F for the dura-0 tion of IW injection (T, = T ) 3 2 IW Tank '/olume Change Date Level Volume Added inches inches gallons 3-4-81 29.0 3-5-81 25.5 1.5 9.0 i. 3-6-81 5.3 25.1 129.0 3-7-81 8.0 22.5 117.0 ( 3-11-81 20.5 9.5 47.0 3-12-81 21.0 Difference between starting and ending levels = 8.0 in. = 40 gal. Total gallons added = 302 gal. ~ Total IW Volume changeE 4' Vgy = 342 gal. f . ~ -.

~ h :- Q s Containment volume at ths start of IW injectioni V1 3 3 V1 = 2,715,000 ft 42.0 psia = 7,757,143 ft 14.7 psia Containment volume at the end of IW injection a V2 V2"Y1~ Yiw 3 dYiw = 342 gal = 45.7 ft 3 V2 = 7,757,143 - 45.7 = 7,757,097.3 ft P2=PVy t,42.0 (7,757,143), 42.00025 psia V2 7,757,097 0 0 T2=T1 = 64 F = 523.69 R t Mass at the start of IW injection E My i My = (28.97) Py (144) V1 = 587,798 lbs. 1545.33 T1 Mass at the end of IW injection E M 2 M2 = (28.97) P (144I Y 2 2 = 587,802 lbs. 1545.33 T2

  • ., Mass change over the IW injection period EE AM = 4 lbs.

l This is a very : mall change; one which could not be observed by the sensors usec" for this ILRT. Based on this, it is safe to conclude that the error due to IW injection is insignificant. 1 l 1 a

o n O O 17 1 Type B and Type C Leak Rate Results 1978 - 1981 ~ Type C Corponents Valve (s) Date Tested Leak Rate (scfh) i 1MOV-CS0003 02-24-81 0.6342 11-15-79 11.43 10-24-78 15.2 1MOV-CS0005 01-20-81 0.1833 11-15-79 4.08 10-24-78 0.5 1MOV-CS0007 01-20-81 0.1544 i ~ 11-15-79 0.17 10-24-78 9.3 1FCV-PR24A&B 02-24-81 '1.782 ISov-25A,B,C,D 11-15-79 15.78 ISov-26A,B,C,C 10-24-78 3.5 1FCV-IA01A&B 02-24-81 0.000 11-15-79 4.08 10-24-78 1.8 1PR0029 & 30 02-24-81 0.000 11-15-79 3.24 10-24-78 2.0 1DT 9157 01-21-81 2.286 11-15-79 11.21 10-24-78 2.0 1AOV-RV0001 & 0002 02-23-81 1.0035 11-15-79 0.05 10-24-78 0.3 1AOV-RV0003 & 0004 02-23-81 0.1284 11-15-79 0.263 10-24-78 0.7 1978 1979 1981 i Total Type C Leak Rate (sefh) 34.5 50.3 6.2

(.. (- ) Type B Components Mechanical Penetrations: Zone Date Testezd Leak Rate (sefh) J1 01-19-81 0.1928 10-17-79 5.97 10-24-78 2.7 J2 01-19-81 0.000 10-17-79 2.51 10-24-78 0.7 D3 01-19-81 0.1808 10-17-79 0.03 10-24-78 2.9 K3 01-19-81 0.000 + g 10-17-79 0.46 10-24-78 2.2 B1 01-19-81 0.000 10-17-79 4.01 ( 10-24-78 2.4 i B4 01-19-81 0.000 10-17-79 2.39 10-24-78 4.7 H4 01-19-81 0.000 10-17-79 11.5 l,, 10-24-78 1.6 Personnel Lock Door 03-01-81 0.000 ~ Seal 09-11-80 0.240 02-02-80 0.953 10-24-78, 0.05 volume Between Doors 03-01-81 0.0973 on Personnel Lock 09-11-80 6.85 02-02-80 1.04 10-24-78 0.88 Escape Lock Door 02-26-81 0.0227 Seal 09-11-80 1.27 12-11-79 0.07 10-24-78 0.17 Volume 3etween Doors 02-26-81 0.5642 on Escace Lock 10-01-80 0.492 01-23-80 0.892 10-24-78 0.31 m. m. --r+- w w-**m9'W+rv-v. hew

    • 1+9e*-,-a

--' = '--tr -*www-wc w *- -r*b, 4-e-w==+- -= =v+ - - t

l O. 19 Type B Components (Continued) Mechanical Penetrations: Zone Date Tested Leak Rate (s efh) Equipment Door Seal 03-01-81 0.000 10-1-80 0.032 01-20-80 0.047 10-24-78 1.37 Electrical Penetrations : 1 01-20-81 0.000 10-10-79 0.000-l 10-24-78 8.0 2 01-20-81 0.000 g 10-10-79 0.000 10-24-78 9.2 3 01-20-81 0.315 10-10-79 0.000 10-24-78 8.2 4 01-20-81 0,000 10-10-79 o,oli 10-24-78 2.4 1978 1979 1981 Total Type B Leak Rate (scfh) 47.78 30.15 1.373 Total Type B Leak Rate for 1980 is the ccmbined leakage of air locks only = 11.816 scfh. ._....y. r- ._,-m,-,,---.___c__,7_.,_-,,..._y -..._-.._..wm. ,,,..r-,.y,.

o..' C G 20 Post IL.T Leak Rates 7 6 of Repaired Items Item Date Tested Leak Rate (%/ day) Instrument Air valves 3-28-81 0.00006 IIA 01A & B i volume Between Doors 4-2-81 O.00006 of Personnel Lock i IW System 4-2-01 0.00052 Accumulator Test Line 3-17-81 0.00006 Valve ISI8961 g Total Leak Rata = 0.00070 s Total ILRT leak rate including repaired items = 0.01584/ day + 0.000704/ day = 0.016504/ day 4 ~ 9 4 e 1 4 e ---++, ,,...--,a.- -,,_o-,. . - _ - -. _ -,,, -. +. ~... -. - ,..,,e- .w.,-,

m. 3 y e

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O-9- 22 bsit$0Y O.4 I0925 S i. - L a s ' & I a,,4 i. n. f i f, ,4 I t s I 5 5 J 5 4 V s 1 8 i s

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5 .s d ,g 23 ~ e -. Appendix A Graphical Presentation of the Results ~ q 4 e + e 8 N m e

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C G 34 4 { o J i i Appendix B Sensor Calibration Data g 9 e e t C O M e 6 e me m_-.

~ c c .q_. voLUMemics 1025 W. AR80R VITAE elNGLEWOOO.CALIFORMI A 90301 P't03E. 8212) nel 3747 PI-l ~ Gauge s.n. 97o Tube Range: Q-100 osia ~ s.n.114Q 0 Roca Teme: 70 F Tube Temt: 50 C Referen::e Pressure:150 m Torr 0 Calibrated by: Z. G. Date: 2-28-81 Calibration Std. No. 07726 Pressure (true) Gauge Reading Pressure - Gauge Reading x M + C esia counts M C 0.000 0.000 / 2 \\ 5.000 4.891 / \\ 3 10.000 9.780 / l \\ A 14.336 13.979 f 5 \\ 20.000 19.562 / 6 \\ 25.000 24.459 j L T / 30.000 29.367 f 8 35.000 34.281 f {', 40.000 39.157 ^ 1.02024286 0.249546342 10 43.000 42.112 11 45.000 44.077 'y 12 50.000 49.004 i 13 55.000 54.049 f ) 14" 60.000 59.037 ) .15 65.000 63.710 ) i 16 70.000 68.450 \\ 17 75.000 73.335 f 18 80.000 78.366 19 \\ / 20 \\ / \\ 2(. {- 22 / 23 \\ f

(:) G VOLUMETAICS nors w.anson vint.inottwooo.cauronnia nosat ewont. 2123 un sin PI-2 Gaure s.n. 9.71 l Tube Range: 0-100 esia s. n. 1517 0 0 Rec = Te=n: 70 F Tube Te=e: 50 c Referen::e Pressure: 15E m Torr Calibrated by: Z. G. Date: 2-28-81 Calibration Std. No. 0772E Pressure (true) Gau8cuntse Reading Pressure = Gauge Reading x M + C psia M C 1 0.000 0.000 / 2 \\ 5.00a 5.022 / 3 \\ 10.000 10.015 / \\ k 14.336 14.275 f l 5 \\ 20.000 19.9.58 / \\ 6 25.0.00 24.937 f 7 30.000 29.902 f 0 35.000 34.854 (- 40.000 39.775 j \\ 1.01206987 -0.0553453743 10 43.Q00 42.752 0 11 45.000 44.735 "/ ) 12 50.0cQ 49.676 \\ 13 55.000 54.739 f -14 60.000 59.749 f \\ 15 65.000 64.427 f ) 16 70.000 69.164 17 75.000 74.045 18 80.000 79.072 f 19 \\ / 20 \\ r \\ (.. / 22 \\ / 23 \\ /

I ~ ( s RTD Calibration Data ~ Ch. 9, RTD 4 60"F 90*r 120*F ft or, .A. or .n. or 1 16 106.76 60.05 113.29 89.93 119.88 120.06 2 2 106.79 60.09 113.31 39.95 119.89 120.04 3 10 106.75 60.08 113.27 89.95 113.83 120.00 4 3 106.78 60.02 113.31 90.00 119.86 120.03 5 4 106.87 60.05 113.43 90.08 119.98 120.06 6-5 106.71 60.07 113.76 90.07 119.82 120.02 7 19 106.75 60.02 113.25 89.82 119.85 120.06 8 27 106.73 60.03 113.28 90.03 119.83 120.01 9 21 106.87 60.05 113.41 89.98 119.97 120.01 10 20 106.70 60.06 113.23 90.00 119.76 119.95 i 11 28 106.72 60.09 113.23 89.97 119.20 120.01 12 22 107.13 60.02 113.67 89.89 120.29 120.04 ( 13 23 106.88 60.06 113.42 90.04 119.79 120.08 14 6 106.70 60.08 113.22 89.99 119.78 120.02 15 7 106.70 60.04 113.75 90.08 119.75 119.98 16 13 106.80 60.07 113.27' 90.01 119.87 120.00 1 17 8 106.72 59.97 113.78 90.07 119.78 119.90 (- 18 11 106.70 60.00 113.73 89.92 119.82 119.92 19 9 106.78 60.02 113.33 89.99 119.92 120.02 20 14 106.75 60.05 113.32 90.09 119.85 119.99 21 15 106.71 60.09 113.22 89.92 119.78 120.02' 22 0 106.71 59.91 113.26 89.98 119.80 119.97 23 12 106.69 59.96 113.24 89.95 119.80 120.00 24 26 106.82 59.99 113.37 90.01~ 119.93 120.02 4 25 25 106.70 60.04 113.25 89.97 119.74 119.91 26 17 106.68 59.97 113.23 90.01 119.78 120.04 27 1 106.72 60.05 113.27 90.03 119.78 119.97 28 18 106.91 60.01 113.45 89.94 120.05 120.05 29 24 106.93 60.07 113.48 90.05 120.07 119.97 i NOTE: Buffer amp settings are aperoximately equal to above (+ 0.05%). tamperature va es I Calibrated by: ['V

  1. \\hk/

2-2-81 / i i (_~;

G' S ( Dew Cell Calibration Data ~ 0 0 Ch i DC i 35 F 55 F 0 75 F OF y F .CL O OF g 30 7 35.70 251.22 55.70 258.10 74.86 264.70 31 3 35.83 249.34 55.51 256.44 75.99 262.90 32 2 35.19 250.05 55.32 257.02 75.73 263.51 33 5 35.76 250.11 55.68 257.61 74.87 263.97 34 10 35.70 249.77 55.79 256.89 75.01 263.33 35 8 35.13 248.93 55.85 255.89 74.00 262.38 36 4 35.50 249.50 56.03 256.60 74.09 262.99 37 6 35.91 250.18 56.09 257.06 74.66 263.46 38 9 35.94 249.01 55.85 256.17 75.34 262.79 39 1 34.77 250.01 55.66 256.54 75.37 263.05 Buffer Amp Set. Buffer Amp Set. Buffer Amp Set. mY mV mV I 3'O 7 35.69 55.75 74.75 31 3 35.16 56.32 75.36 32 2 35.09 56.39 76.00 33 5 35.44 56.52 74.17 14 10 34.81 56.10 75.15 I s5 8 34.86 55.13 74.00 36 4 35.06 55.88 74.49 37 6 35.38 55.95 74.85 38 9 34.80 56.04 75.47 39 1 34.57 55.39 75.91 I NM rkD 2-23-81 Calibrated by: G / C

i l ^ (. h VOLUMETRICS i CERTIFICATE OF CALIBRATION ' Attention COMMONWEALTH EDIS0N Date: 12-10-80 ] ZION STATION Test Titi*. RECALL DATE 6-10-81 PORTABLE PRES $URE CALIBRATOR MODEL #07726

References:

Purchase Order No. 921608 i Volumetrics Job No. u(/6446 Serial Number 1061/1914 { Government Contract No. 1 ] Gentlemen: i This,is to certify that the enclosed Test Data Sheets contain g.. .. correct and true data obtained in the performance of the test program as set forth in your Purchase Order. Instrumentation used in obtaining this data has been calibrated using standards which are traceable to the National Bureau of Standards Calibration Procedure: MANUFACTURER'S SPEC. Reference Standards Used EQUIPMENT NO. CALIBRATION DATE OUE OATE VMc 906/1915 11-7-80 5-7-81 4 i, i i j Enclosures Data Sheets ( 1 Pages) Ous11ty Control Approval: (//77Ihb$ j K.A. CHAM 8EAS VFORM-10024 .e,_.--.-- .-.,.___,__m.,,,,,._y.,,, y...w,._.,._,,,m.,.. ,,yy, ,.,n._,m-y-_, .,,,rw,,-_,,&.,,,,,.,wm-,w.m.,c_,yr-m-._

(i .s V O L I'.t M LE 1 R I C S ENERGY SCIENCE CENTER P.O. BOX 2034 PASO ROBLES, CA. 93446 (305) 239-0110 c CUSTOMER: COMMONWEALTH EDISON (ZION STATION) GAGE S/N 1061 CAPSULE S/N 1914 RANGE O TO 100~ PSIA DATE 12/10/30 RECALL DATE 6/10/31 STANDARD NO. VMC 906 ROOM TEMP. 72 F CAP. TEMP 50.3 C CER. ACOUR. 0.015% 1 VMC JOS NO.07/6323 CUST ORDER 921603 CAL..BY M. GREEN .5 TRUE PRESS. = (GAUGE READD 10 m M) +C POINT TRUE PRESSURE OAUGE READING -M- -C- ~ 1 .000 .000 .93951 .000 2 5.000 5.053 .99364 .021 3 10.000 10.005 .99562 .041-4 15.000 15.107 .99364 .011 5 20.000 20.139 .99483 .035 e 6 25.000 25.165 .99522 .045 7 30.000 30.139 J- -1; 1.00040 .201 3 35.000 35.137 .99741 .096 9 40.000 40.200 Q99602 .04 to 45.000 45.220 1.00705 .539 11 50.000 50.135 ~~ 1.00120 .245 12 55.000 55.179 ' ~ 1.00533 .501 13 60.000 60.150 ~~ ~ 1.00644 . "A3 14 65.000 65.113 1.00402 .379 15' 70.000 70.093 1e00462 .422 16 75.000 75.075 1.00261 .271 17 30.000 30.062 1.00746

  • .659 13 65.000 35.025 1.00261

.247 19 90.000 90.012 1.00422- .392 20 95.000 94,991 1.00422 .392 21 100.000 99.970 PAGE 1

e s b -x. ~ E O V E R R. J i_L\\ 0 0.2 cc d 729 EAST WILLOW STREET t LONG BEACH, CALIFORNIA 90806 424-8533 636-4096 CALIBRATION CERTIFICATION suausTTED BY: Volumetries 06 FLOWMETER SERIAL. NO TO8E NO R9H 2S-1BR 3/4-14G MANurA CTUR ER Broob WrG. SERIAL NC' 7204-80097 I D/R External Scale, Calibrated in SCTM Air @ 14.7 PSTA & 70 F aEMARxs: 0 ACClJRACY 21% FS IN DIC AT E D' ll A CTU A t. SCTM SCFM s 17.a 8.135 ~ 1s.U 0.444 1U.U 4.44a 0.U i 4.0V/ I' 4.U l U.yed l I I I ( l 1 Flow m e t e r Ce rtified with HOMER A. CULIN CO. 12401 0.2% 6/81. tw'oceat No. % nrcy CelW M83 No. Cert. No. Our stenderds are s o rtifie d by er are trecealble to the Nattenol Bureev of Standards and comply with, M i t.- C

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i 9-9 VOLUMETAICS { CERTIFICATE OF CALIBRATION Attention: COMMONWEALTH EDISON Date: 9-31_a, IION PLANT Test

Title:

DEWPOINT CALIBRATION

References:

Purchase Order No.' scotan Volumetrics Job No. nnf4tvt ,1 Serial Number ne neure,.. 472 i Government Contract No. u ra Gentlemen: This is to certify that the enclosed Test Data Sheets contain correct and true data obtained in the performance of the test program as set forth in your Purchase Order. S ~ Instrumentation used in obtaining this data has been calibrated using standards which are traceable to the National Bureau of Standards Calibration Procedure GAP #2002 Reference Standards Used: COUIPMENT NO. CALIBRATION DATE OUE DATE VMC 202 10-3-80 10-3-81 VM: 209 11 4-80 11 4-31 i Enclosurss: Data Sheets ( 3 Pages) Ous11ty Control Approvals . 0

  • f. 0%*$(.M' K.A.

CHAMBERS VFORM-10024 e

{ VOLUMETAICS 4 ~ PROCEDURE FOR ALIGNING 660-51 SENSOR ~ WITH A MODEL 660-C1 ELECTRONICS This procedure refers only to the control loop performance. The PRT bridge amplifier is already aligned and need not' be readjusted. Model 660-C1 electronics and 51 sensors made for Volumetries are d,irectly in te rchangeable. However, it is necessary when a new sensor is attached to the electronics, to maka certain adjustments to the dynamic control loop to match them properly. The following procedure is used for this purpose: 1. Check R42. If it is a 15K chm (1502F), it should be paralleled with a 5.11K ohm (5111F) resistor, or with a 1.10K ohm ~ (1101F) resistor. 2. Set,the THX potentiometer to full counterclockwise position-g and the "como" and " gain" po ten tiome ters to position 3. (Turn full ccw and then 3 marks cw.) t 3'. Clean the LED, photo transistor,. and mirror with Freen TF. Clean the sensor mirror surface with Type A cleaner. (Lemon (. Pledge.) This step puts the circuit in the manual balance mode. The circuit will stay in this mode for approximately 1 minute and 20 seconds. It can be initiated as of ten as necessary to i coeple te the alignment. There are two ways to put the circuit in the manual mode A. Pressing the MANUAL BAL ANCE INITI ATE and t' he MANUAL ~ BALANCE INTERLOCK simultaneously. B. Briefly disconnect line voltage. 5. Measure the voltage on TP7 to ground TP6. This voltage is the voltage to the LED and should be around 2 VOC + 0.5 VOC. 6. Measure the voltage drop across R3 and R4. Both should be 11 VOC + 0.5 VOC with the circuit in the manual balance position, and the mirror dry. 7. If either R3 or R4 show a voltage drop of 12 volts or higher, turn R60 ccv until the highest voltage drop on either R3 or R4 is 12 volts or less. This adjusts the LED current. Be sure tha t the electronics are still in the balance mode. C T.H. 11-19-80 Rev. 1 Page 1 of 3

C C VOL.UMETRICS ([' 8. Attach one c'hannel of a dual trace oscilloscope to TP3 and ground TP6, and ad.just RIO until the voltage at TP6 is 2 volts + 0.2 salts. Se sure that the electronien is in the manual balance mode, tha t the electronics in not,trying to balance automa tically, and that the mirror surface is dry. This measuremen t may change if the condition of the sensor changes and the manual balance mode is restarted. Leave the probe on TP3. / c9. Measure TP1 while in the manual balance mode. It should read .03 to .05 volts, indica ting that heating current is flowing in the s,ensor. There is no adjustment on this measurement. 10. Attach the second channel of the dual trace oscilloscope to R30. It should show a TTL logic high (approxima tely 4.3 - SV); this is the automa tic balance con trol ( ABC) line. As the circuit completes its 1.4 minute timing cycle, TP3 will g go to + 12V (approxima te). It will then start to decrease to - 12V (approximate). As the voltage at TP3 approches zero, the ABC line should trigger and go to zero volts. If it does not, wait for one more cycle. If it still does not trigger, the 660 C1 board adst be modified by ' paralleling 0.01 MF capacitors with C13, until the system continuously { triggers ou t of. its ABC mode. Allow the instrument to time i out its automatic balance cycle and re-zero itself. As soon as the electronics begin to cool the mirror at its i maximum rate, and before any dew has collected on the sensor mirror surface, measure the voltage TPl. This is a measure { of the maximum cooling current to the sensor in the operate mode. This value should be adjusted to 0.10 VOC (which is eqtivalent to 1 amp) by ad.iusting RS6. 3 11. Attach a calibrated precision digital voltmeter (such as the Keithley) across Pins 5 and 10 on the rear edge connector. Pin 5 is directly opposite Pin 15. 12. Connect a resistance decade box as shown in Figure la o a o( )o 10 Decade Box C e - ,o o i Bottom View Figure 1 T.H. 11-19-80 Rev. 1 Page 2 of 3 e -..... -

.- _ _ ~ h. h.1 VOLUMETRICS 13. Set the decade box to 100 ohms. 14.- Observe the output of the DVM e,ttached to 5 and.10. It j should read 0.000 volts. If not, adjust R97, "zero" until DVM reads 0.000 volts. 15. Set the resistance decade box ts 117.59 ohns and adjust ,R13, " span", until the DVM reads + 5.000 volts. 16. Set the resistance decade box to 139.89, ohms and adjust R100 "lin"* (l'inearity), until the DVM reads + 10.000 volts. i 17. Rapaat Steps 11,12; 13 and 14 as neces:1ary to bring s ach voltage reading to within 2 0.010 volts of tne values Each adjustment interacts slightly 'nith the others so 'given. it is sometimes necessary to repeat' these ' steps several times. 18. By setting the resistance decade box to 80.10 ohms, the ? g .. lower and of the scale at - 5.000 volta can be checked. 19. Set the datalogger to the appropria te channel.. Se t the C range to F,' or 10 volts, if the display blanks. (~ .2 0. Set the resistor decade box to 100 ohms. Observe the gatalogger display. Adjust the "zero" potentiometer on the F conversion card for a reading of 32.000F g 0.18. 21. Set the resistance decade box to 138.89. ohns. Switch the datalogger range to'10 volts. Adjust the " span" potentiometer on the F conversion card for a reading of 0.21200 t 0.00018. 22. Disconnect 'the resistance decade box. Initiate o manual balance cycle. Set the detalogger display to CF. The circuit should lock in on the dowpoint in about 2 minutes. l Monitor TP1 with a DVM. If it appears to be oscillating (largeMonitor TP3 with the oscilloscope. swings in voltage), increase the compensation by turning the "como',' po ten tiome te r coun te rclo ckwise. sligh tly. It is also possible to adjust the " gain" poten tiometer clockwise. Te chnician : M Approved By: 8 M I4V

0. McKie Date:

K. Chambers 5-94-n* Date: C 2-?c-n1 T.H. 11-19-80 Rev. 1 p.g, y,7 y ,-e. ... ~. . - ~ _... -,, _,.. ~, ..._,,-f,

7 4 i ,f ~ STATEVENT dir CONFORMANCE i ( YOLUutTRICS CERTIFIES THAT THE USTES EculPMENT ANO REoUIRED 4 ooCuutNTArton PoR THE sAut utET THE REcutREutNTS OF THE PURCHASE oRoER AND APPUCASLE SPECIFICATIONS.. s = = CUSTOMER: COMMONWEALTH EDISON COMPANY-ZION PLANT . 'T., 921608 P.O. NO.: REV- "#^ SPECIFICATION: N/A R EY. N/A WORK ORDER No.: 07/6328 (INVo!CE NO. 8361X). i DESCRIPTION OF E'QUIPMENT: RTD & CEWPOINT CALIBRATOR g 1 i C ~ l l IDENTIFICATION: A. lTEM RTO S/N: 76448 DEWPOINT SENSOR $/Nt 406 s EQUIPMENT M/N: 07731 l d. voLUMETalCS REPRESENTATivt Q.A. MANAGER C TITLE JANUARY 9, 1981 Cart VPORM 10072

h* .7 vcLOMETmica s CERTIFICATE OF CALIBRATION Attention: COMMONWEALTH EDISON Date: 1'-7-81 ZION PLANT g. Test Title s, RTO CALI5 RATION FOR MODEL 07731 g.

References:

Purchase Order No. 921608 Volumetrics Job No. 07/6328 Serial Number 76448 Government Contract No. Gentlemen: This is' to certify that the enclosed Test Data Sheets contain .. correct and true data obtained in the performance of the test g program as set forth in your Purchase Order. Instrumentation used in obtaining this data has been calibrated using standards which are traceable to the National Bureeu of Standards Calibration Procedure: QAP #2003 Reference Standards Used: EQUIPMENT NO. CALIBRATION DATE QUE DATE BURNS RTD 84938 11-3.-80 5-3-81 VMC 209 11-4-30 11-4-31 VMC 202A 9-22-80 9-22-81 ~

Enclosures:

Data Sheets ( 1 Pages) Quality Control Approval: c Nadachd K.A. CHAMSERS VTORM-10024 m -,--,n--,,-------,--n

..,. _ + -

== ('. ; Q) ~. :- i VO LU,M ETAICS l RTD CALIBRATION REPORT .3b8 NUMBER: 07/6328 ..'o A ig : 1-7.. MODEL NUMBER: 07731 0 CERTITIED ACCURACY: 0.06 F

. REQUESTER: COMMONWEALTH EDISON-ZION PLANT CALIBRATION STANDARDS USED:

VMC 202-A 8 209* BURNS RTO#84938 Note: All-standards used in this test report are traceable to the ' United States Bureau of Standards,, Washington, D.C. ^ NU ER 6 0 F. 90 F '120*F h 82 5 1 L 76448 l Sept-75 106.198 OHMS 112.746 119.257 I 0.0185 RESISTANCE OF S STANDARD: 106.171 OHMS 112.760 119.098 0 0 ACTUAL READIN3 59.96 F 89.980, 3 3 9, 9 9,' U i l ~ .I e e c TECHNICIAN: _ rMw Mu 7)J QUALITY ASSURANCE: [fM 1 J. SADGETT K.A. CHAMBE'48 _,_,_l ~

A (. r Summary of the Initial Test The initial leak rate test which started at 1830 hours on Monday, 3-2-81, was aborted when a number of leakage paths .- prevented successful completion. The least square plot of this initial leak rate clearly demonstrated potential problems ... 7 hours into the test. At this point, all efforts to identify leakage paths proved unsuccessful. Three hour.9 later, the leak rate had leveled out at 0.124/ day confirming earlier indication of a potential problem. From this point in time until the restart of the ILRT (9 days later), numerous steps were taken to eliminate leakage paths. These steps are summarized in the Log of Significant Events of the accompanying report. Furthermore, sensor responses. I .were trended and the calculations reverified to insure correct-m ness in this area. Only two dew cells and a pressure sensor s i were locked out prior to the start of this test. Therefore, { the figure of merit for this case is more conservative than the results for the final test. The final test figure of merit results are well within the acceptance criteria. F e .= d 6 0 . ~... ....n--

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