ML20087A220
| ML20087A220 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/20/1968 |
| From: | James Keppler US ATOMIC ENERGY COMMISSION (AEC) |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086U000 | List:
|
| References | |
| FOIA-95-36 NUDOCS 9508040230 | |
| Download: ML20087A220 (9) | |
Text
.
N [s
^
5.
'}*'F W.W: % ~MS L YY
~
~"
' '~ *~"~
1-3).'
Q hadu,~ J A _ l . in ~ ~ cs R 2d/GiH ~ u i June 20, 1968 4. i J. P. O'ncilly, Chief. Eccctor Inspection ~ l cad Enferecuent Branch Division of Co=plianco i:I!!:CCG Op CC::PLIN:::;-InCCY CENTML Pot.'IR & LIGIIT CO: ipa:iY ikECT1tG,' __ g 1:.W 15,1903. 070m CLM L'UIT E0.1. DO:: ET No. 50-219 Y A cc: tin 3 c=on; rcpre.:catativas of Jcracy Ccatral Power 6 Light Co=pacy, Cener:1 I:1cetric Co.-pccy, cad cc=plicnco vcs hcid et tho Oycter Crcck cito on 12y 15,1953. The purpc a of the c:cetina was to discuss opt-standin; is uco relcting to the preoperctional testing and initici fuci loadins prcarc==. /.ttend cs at the c:cotina vero: Mc-co JCr$L i E. T. Carl en T. J. 2: Cluckey J. G.-Ecppler I. R. Finfroch F. J. Colan D. E.12 trich l l P. P. 011vadati 4-COS ULTA!ES i s, K. U. U 03 F. Schucercr, Pichard, C. E. Forc= n Lowe G t.scociates T. R. Eobbins, HUS Corp. This c:ctin3 vao a follow-up to an earlice ccetins hold on January 30,196S.* A cc :ary of the principal ite : diccu::cd and the degrco of progrc s c:cdo toward 1rcsolving the e 1: cues is provided in the enclocuro. Ice =s requir-in:; further follow-up by CO vill be covered in futura inspection reports or subsequent meeting minutes. ^' The post-loadins sesrtup testi=3 progre:s was not included at this aceting ) pendins further review by Co. It is plcnned to discuco this proarca, along with the rc=sining outctandin3 cc: tin probic s. in depth with the appli-cant and C; ct a fut'uro meeting (probably in July). op Acy% .4 J. . Keppler, Senior Eccccor Ir.:pcetion Epccin11st
Enclosure:
Divicica of Cocpliance Principal Items of Discussion s, 'cc: R. T. Carlson w/enci
- Minutes of this earlier cecting vero issued cn ;'(.,r.. cry 20.. _ _
hN e A.J.i 9500040230 950227 PDR FOIA DEKOK95-36 PDR
. G,. ;y;; l,',, - -'8sOh%:..IO}P*IRlf.f f t sg - ~ ., c + i f.~* *: ',- *. _, J., [
- ., - 5.
A
- - -"_L*'_'.^
g \\ ^,,. a 4 g r-e PRINCIPAL ITnts OF DISCUSSION i PREOPERATIO'ML TESTit.'G Ah*D INITIAL FUEI,1.0ADING FROGRAMS ?- l (Nesting with Jersey Central Power & Light Company May 15,1968) l 9 A. Preoperational Testina m
- / '
'1. Control Rod Drive Testina a ? January 30 status - CE's program for control rod drive testing" was not considered by CO to be an adequate a checkout of the systesa prior to operation. The major } concern with the proposed program was that no testing i was being performed at elevated temperatures prior to
- 4 nuclear operation. In light of CO's concern, GE agreed
+ to review their proposed program. ~ l ~ May 15 Meetina - Foreman outlined CE's modified prograu i of control sod drive tasting as follows: Fuel in Reactor , ypf(sa t**'?M Power Mo Fuel Anr-300 600 1000 Assen-1001 i fest cold bient nei ' osi osi eion Power i r Friction All All ee Scrau (normal shargo) 5 times sa. All 4 4 AHAP '
- All i
scram (minimun charge) 4 4 Scram (sare charge) 4 v > High Ievel 4 In/Out - Timing 5 times es. 4 -a, i Overtravel 8 times aa. All 4 i Fosition Indication 8 times ea. All 4 l All Bods Scram 2, 4 1 r., frl / u g, CO Report No. 219/60-1. r. Following the individual control rod scram tests, the slowest and
- fAlfilt drive.s wi.ll r3cei.v.e an.a(ditlfmal.23,scrama eseb.
ter tu an pr r ~ rat ows,). .~ I e-a ) 6 e m--awewe>- - - -- e-
y.---m2
---wn--.m _w-.,-2.s w.--a.r-.e-my.-'
. 13.'? ~, ~ .- J.. & . I. t 1 '.,.S y [i.w., - ] { e / ./ J. F. O'Reilly _ ~ While this Prograra represents a definite improvement, particularly in the number of cold scrca tests, it still did not incorporate usaningful t sentrei rod drive tests at elevated teoverstures (nonnuclear). In l support of this, GE personnel rce:ghasized the testics that was performed in a special a:och-up rig at San Jose in which the Oyster Creek control N rod drives were tested under normal and anticipated abnormal operating conditions. They also pointed out that possible probicas resultina from thermal expansion were not considered to be likely becauce of the design i toicrances. CO acknovicdy:d the above, but stated that there is still concern for the following reasons:
- 1) many unsuspected problems have been encountered with control rod drive systems in general, 2) that the level of experience attained by C3 to date is not sufficient to lend con-fidenceithat probices will not occur, and 3) that the Oyster Crack drives arc ~three feet lon;cr the.n the K.u drives. CO firmly restated their original position that thc control rod drive system cannot be considered 4
fully checked out with(Ecucfft of meaningful in-place testing at elevated temperatures prior to significant nuctsar power operation. CE is currently reviewins'the control rod drive preoperations1 test pro-gram in light of CO's stated position.1 In rcuponso to certain coaccrns raiced by CE, and agreed to by CO, the control rod drive testing during tho fuel loadin3 program has beca slightly, modified by CE. All plannod control rod drive functional testina does not have to occur attor the control' cell has beca loaded. P.owever, prior to making any accccpts to achieve criticality, each control rod will be fully withdrawn twice, driven in once, and scrar.asd once at ambient temperature conditions. The. scram test will be' timed. 2. Vibration Mensure:-entn of Reactor Vessel Internsis Jstue.rv 30 Status - The procedure was considered by CO to be deficient in that measurc=cnts on the steam dryer assembly ^ were not included and that testing acceptance critoria were { not cpoeified. CE agreed to reexamine the test procedure in light of the concern aspressed by CO. } P9v 15 !!~' tim - Foreman stated that the vibration measure acnts prc; ram had bcon expanded to include censurements on / the inlet flow diffuser under porturbed flow distribution ~ conditions. s' Vibration mescurements on the steam dryors were considered by Ga and rejected for the fo11ouir.3 specific reasons: 1 4 m-, _m,-- u- - -- + --. -ew-e-.---
- ^
='P,** f = q,V-
- -+ - *.m p, ': - t ; ' ' * * ' ~ ~
?J .f, ,, ? } g ., ' _.;,- O 'n. \\ l Af J. F. O'Reilly ' L 1 s a. The loadings on the structure are considerably less than j the ultimato strcesth. b. Vibrations are not expected becauco of the small driving i forces thrcch the dryer vancs Echroo ic/sec). i c. Air-vater flow tects o' the Oyster Crack type dryer vanas have shown no vibrational tendencies. CE's evaluation of this matecr vill be reviewed with DEL. The suSject of test acceptanco criteria was not discussed at this meeting and will be pursued during futura vicits. GE has stated, however, that acceptance criteria will be incorporated into the test procedure. 3. Peactor vennot Safeev Valves Jn: unty 30 Sentud - CE had confirmed that the safety valves would ' bo bench tesccd at the sito prior. to inctallation. This was acceptable to CO. I'ny 15 iS9tini - Ecos ccated that the valves vill now bo set at che Crosby plant in 12scachusetts chortly boioro installa. tion and that cortified vendor test records will be provided. Ecss pointed out that a receiving inapoction would be con-l. ducted to assure that the set point has not been disturbod. CE war told that this approach is also considered acceptable to CO. 4. I.iquid Poicon Syste, Jnnuary 30 Statttn - The test procedure was considered by CO to be deficient in thct the cystem's injection ccpability i uss not bcios de=onstrated under operating tc::perature and I pressure conditions. 1 Iky I5 M1ctin; - Hess reitersted CE's position in January that such a test is ennecessery becauso the cystem utilir.cs poottive displacc ~.ac pu=ps. CD rointed out that the pressure differ. cacial betucca this cyctea end the reactor was less thaa 400 psi and that it uns not incoccciv:blo that the systc=s check valvco nicht stick. CO c;gh : iced the i=portance of testing c a l:ccred c fe;uards cystc:s to the Lu11cce extcat prceticable ar.d ooted that chare was no ic;ical recton for not performing -~ -
1 ~=w w,. r.:., z y. .w.ws:.g.upr; , ; *, e -~ f 6 i q ~ . 'g.,., W i \\ -y J. P. O'Reilly ) a the test. C0 su=narized their position by stating that tlpe syste:n could not be considored as checked out unless it van tested under' operating prescure conditions. 4.,' Another review by CE is being conducted. 5. contair.-ent S :rny evte, J..r.m r 30 Stcten - The test proc::durc van considered by' CO to be deficient in that no quantitativo dccionstration of flow dictribution was boing m2de. G stated that this , matter would be revicued. iSy 15 t'ecti~t - Flou cud pressurc drop characteristics will be evaluated on 20 nozcles in a specist test facility. A qualitativo air flow test, using stres::nrs to verify that no gross plugging exists, will be applied on the rc=aining nozzloo. On tho' basis ~of these tests, supplementing the total syste:n flou cescurements to be conducted in the bypass loop, c2 una cold that this psgr=:n is now considered secapt, able by CO. 6. _125 vote D. c. Sy.ete, 1 _Jnnn:rv 30 Status - The test pro; ram was considered by CO to bo incdogste in tbst it did not include a capacity test of the batterics under desian load conditions. CE agreed to review the r.atter further. ?%r 15 f tectimi - U::ss ctated that a ccpticity test of the batterica would bo perfonsed under a load of 47.5 hp. Althou;h a positive encuor cculd not be provided in response to questions concerning the e.axic=:a load rceirc= cat under accident conditions. CD and JC perco=not stated that the 47.5 hp load was arcator than the 13 load. Ascuming this is the casa. CO considers the tcot of this system to be satiofactory. Co.will review the W.:A load requirements for the 125 volt D. C. systeca. .y i t 3. Inecerated Ptection,1 7.~-t Jan t: rv _29 f*:nttq - CD pointed cut the cced for a sustained inte-Crated inactienal ccet !..:c;rc s pric to real loadin;. including hot testina to the dcarco practic.1. Addition:lly, czphaois vss placed on the icportanco of ticin; in personnel trainius of the Jersey Central operating crews to this test prones:n. CE-JC representatives agreed to revisw the subjecc in light of CO's comments. 4 e 4
ly_f. p' n.- ', - M y;k %,w.w.%%;~ nmp:44up'gynf@y O s: lQ'.{, -}, }
- .~ m,..
_ _. _..s i /: { , m p.,. + J. p. o % 111y. '. May 15 l'ectim - CE supplied CO with a draft describing the scopo of the integrated functional test program which they had l developed. Basically, the intended program coveres n a. An integrated systes test will be perforced in conjunction with the Pri=ary Syste:2 L: pension Tect. The reactor and recirculation loops vill be hected to rated tecqcrature and procsure conditions and hcid for $6 hours. Eccause gf the largo heat los cs which would be icposed on the pricary system the reactor cicenup system, centrol rod drive system. and ccergency condenser system will be isolated. The reactor cleanup system would be placed in operation toward the end i of the test to observe systcra performance. b. Following cooldcua of the recetor vessel, a loss of coolant ' f accident concurrent with a loss of pouer will be simulated ^ to dc=onstrate the satisfactory operation of the required equipment. Tho ' core spray and containment spray systems will be valved to rceirculate,the water to the torus, but will otherwice duplicato norms 1 system operations. CO qucationed the desirability of performing the test from operacius'tceperatura and preccuro conditions. !!ase assured CO that the dc=onstration perfor=anca was virtually just i as conningful from the cold condition. Prior to fuel loading l CE intends to operate the diosc1 generator with the maximum quantity of nicetrical equipment in operation. i c. As part of the intcarated functional test, a primary systoa leak will be si=ulated by injecting steam into the drywell. j The test will, in part demonstrate the ocasitivity of the sump pu=ps to dcccet increases in Icakage. CO noted that i the calculated Icakese frca failuro of a control rod stub tube van 5 spm and that Amendecnt 37 implied that auch Icah:3o would be readily detected by the su=p pu=ps. CO il co= ented that verification of this detection capability. 4 ~ as part of the test, vould provide meaningful informatio. CE stated that they would consider this matter. ' " ' + -r In diocussing the simulated pri=az/ system Icak. CD raised many - / questions regardins the operction:.1 cud F.:.rformance requirc= ants of f, the automatic deproccuriestion cystcu. It vac r. ted that this system 1 4 is now with the Cyster Crcch plant. C0 q ::tioned whether CE had [ given consideratica to tc 063 of this cych:s under rated pressure end l tc=pcratura cc:diticas. c;ain pointing cut cho inportance of thorough ',',7 I testing of ensinocred cafety systccs. It was appercut that this test. had not beca previously considered by the CE reprocentatives and they agreed to give serious consideration to this matter. C0 will follow ., s. i
s.. - ~ ~ - + y; % Q.t._g,.. _. .y-., v;r:L,u.:.4 m.:.. Hl.p ;.ee
- p
.e t gg y 4 t. W-1 A c. 4 _.. i i
- t..
'J n.: It-. J. F. D'Asilly 0- ~ - In general, CD bo11cves that as much of the reactor systeus are co11cetively being tested as practical and thereforo considers i che scopo of the integrated functional test to be adequate. a CO gj will follow up to ascure that adequate procedures are issued in y3 support of these tests. C. 7nitini' M1 Imdhn Jamry 20 Stat s - CD infor=cd CE that the fuel loading procedura 1 l veo considered to be in:dequato and highlighted several deficicacies. particuinrly in the area of administrative controls. CE agreed to revicu the loading procedura in light of Co's coc:conts. liny 15 tSeti m - A reviced ecst prcarem proceduro was presented to CO for review. L is now procedure was noted to have satisfactority responded to the following prev'ious CD concerns + The nu:aber of chutdown m:argin demonstrations has been in-a. creased from five to 16. b. Screa Icyclo for the nuclear instru=antation have been defined. The neutron cultiplication will be continuously plotted during c. the loading. Renormalicceion will ba done following dctcetor covc= nt. It was noted that no s=ntion was cu:da that fuel loading limits would be conservatively established based on I the count rato data. CE stated that this would be done. d. Tho minicu:s critical core configuration, with and without poison curtains, has beca i=corporated into the procedure. x e The design capability of each control rod' drive will be e. dc=onstrated with fuct in the reactor prior to initial j criticality. f. The administrative procedures have been incorporated either directly or by reference chects which will be attached to the procedure. Contnic==nt requirc= nts, health physics coverago, / ctaffing, palifications, work hour limits, and procedure chan review requirencats will all be covered according to Foreman. ge CD will follow up. A facility system checkoff sheet is being incorporated as part 3 of the loading program.
~ > o 4,1 q f.v..m' g y 3 -w r t ~ a X ~i-- 1 +.M. 9 ^ d I .m r~ '?- ~ + _,s q A;.. c. 2 ~, '=~
- < a
._..yy.;g ) m. y 7 . e .-c i i ~ l J. P. 0 % illy.. ! i
- h.. Health physics requirczants have been incorporated into
'l kho proceduro. i .,e 1. A pro;res for cporator =d fuel Ic: ding equip =ent check-s a A"' cut'vi!1'ha conducted. The in:pection procre.:2 for cach j fuct cccc=bly has not been fir.211:cd.' CD will follow up. j 1 a l The revised procedure.ucs noted to contain no significant now in-for:2 tica cor.:crning the boron cesinic:s secol poiron curtains. The individus1 curtains h:ve not bacn tc:ted for. poison verification. li i This subject was discucced with C2 and the following pcrtinent in-l formation was cbtained. ^ a. Approxi=stely 10 percer.: of the poisen curtains voro checked i durina the mini =n critical coro tests perfotzed at vallicitos.- +' i b. The poison curtains core febricated fres seven hcota of steel. Esch heat of stect was chocked for proper boron content by mass-spectro =tcr c::curc=acc. c. Thero cro two groups of curtains-- ~4100 ppa boron cd 4300-4403 pp:a boron. - d.. A sic;1c poicon cerip not contcinin; boren, when believed { to coatsin boren, would be of significance. Depending on the coro location, this condition might not be dctcceed and. local c;olting could rceult. ( l i The reactivity vorth of the poison curtainn is approximately i a. e. 10 percent a k/h. 1 i Eaced on itc=s d. cnd c. C0 stated that verification (e.g., a blackness tect). of the poison content in all curtsins appeared to . / f ^ l be rcquired. CE.o;rced to revicw this c:tter further. , i + i Jersey Central personnel were ached to what degree they had or i ucro participatina in the rcview of the fuel loadin; proceduro. ) Alth:=;h so=o state =ents vero cado rc0ctdina a revicu by the Picut Operations Ecview Coc=ittes : the depth of this review and the role e of tha Cen:ral Offico Ecvicw toa:J could not be clearly ascertained..
- j
%his cubject will require further review by CO. l o m m., .,s t
!~ M8AkeWM j.A, i[. 2 s. L.,af. - b. 4JdA. e A s.1,.,,,,.m d,L..u_ 4 m, 3 g* r g . "1 [ yj f r + NOV 211968 s [a) ' I .l. y .p -s.'., -r.~ su. 4 .M h , m.o. e s ...e !... i .. i t. .. ~-r e L _#. ~.e. O- , L.g / T ~ v a s. .Y.- .s a. ..,3.. ,, w e,. ,? a. . u .. +.. J. s,v., ,, j..
- r.,.
.~ c l , b - s ,e e + s ^
- e n
. J e %s T.1. i* 8% o'$ c .1.. 0; * '.,. p , c,.. .. g. o _.. t.. t ,..s, >.i. . 3 6*e.*....., L o 4,.,y.- m. .r *,.., i V ';'T,y. - ss, e y.,, .o w, k,n. sa.,1 .s '. w.,... q w. - ~-......,5 e,. ., [ f .*/ 4. .t..,. 4 t,, w..
- g-w...
s...,,,,... ..t.. ... _- s g a ...e. .w r.
- e
... = ....s..,.... " i i --
- r. $
ee.e.d. e g. =-
- 4... -
- 4. -e e
e pe e.e e i r g a l 'vW .e .,q m J, v. ,a
- 6.
I( = f '. 1 +... 4. s .r j .I e#, e,. f e w. .) 1,$. ,.s i b e= e e s. a3,*.. j e w.e ..e q p. 33.h.'. t .e.,
- =.
e a p.m w.. ey .. w e en as ha s-4' f e v., ' C.*.a.. e.. 3 e., .,,.....%.y s.s.s..... p m... .,M
- o.f
- y. '- O,
,a ..a p m ~. . v.,, ...&p. bw ehw. -4 . t '.e ,.6 i W. I -=..... w .4...
- a.
t 5 . 4 i ?*
- s.,
i
- b 4.%
w -e.,"sa 4 h tr +,
- , f 8
k e d e .s v. p t + Y g.. i I I A ~.. ..s.. t n ~~ 4...... g ~* A% %.
- 3 a
j ~.$ /...,' 4 4 w,, y C.,,.,... w. g
- e
+ - s
- i
.b.b. 4.. w .k. .f......1
- =$p
..,.... L s .4. 4. s..<.J. r r.**e.. .,a s A5 b d b [,a b 4. ....i w, -,,.,.f 1,. I &w aa.8' 4e g =. '. '.7 ,4,-
- .., 4we e.,
m.m. h.L.4. h. ei..x ~- g .s3l' .,..~_.. .-..p .3 ... ~. a J.,.. o s.... r .s,a .s n i , T. .i .;J s -gt t, - $ c-9. C 1.S.**L. 4, a.a.. g s i w *- p , - e r Lg. n, 'e-. ^ iw ..w e 0 I eeg ..f.eP-1 w. g ag S
- e. p.e J., ) *
'g ~,9.. jy ,I --3 ._g i t } .NOL2-2,-196g -'O / ' i i n M=
- a..
v. 9 ',F* u .m.m.v, u ra: o.. 4 s S eep .g> 2 w pp.am.6ag..,.w -- e e.orgym+.am- .e, .._~.* -. ( p e ~ v m r-r.
/.,- a c ,L } g 9 /- 1, 2, N0Y 211968 i. ...._a. 4 4, ....s2,. 3_, o ..-.s. r,. ~.._ m. .u.. .s..... x v. ,....1 ..ir, ..s r .__....a., ,.. a, c .g (, ....u..,. t. ..,r. u. i. g s e...., .... ~ - w. c ., pc 7. .,~ .a 3 y .. 2 .. \\.. -__s .......4 .(..., s s .u. .y ..g.,.._. , ~.. c, s. . _..i..-.,s. =...... ; t.- -m ,,s,. .... a la., -. m. Or,-'- -i !. - M i V. R. H. Eri;ciken v. 2... J., . L. c~ .a r.-. .A r. 7. >,e ,,).~ .v L,; !C F J., ." a ~ (. e ~.....w .3.. (.. )s .'s s. 4 .' '. 's.,...:., G. .a. v \\ .s .a s.,. u. s.. ..,. ~. t t l
- cc
- / v/enel E. Caricon, CC:I i,
j 1:. Mocc1cy, CO:I
- 5. Thornburg, CO:III G. Fiorelli, CO:III J. Flora, C0:IV i
G. Spencer > 00:V F. Long, CO:II v/o CO Inep File C4DCE a.. ..C.. C. .......l.. ..C C......... - ..............i.... ~ J.. nlcr:c,) .y \\, ~< ~~ 1., 7m., y ' ...t.~~;*,*.1,~ ~ ^ n. - ..I. 4. 1 j ..p l '. =.
- .-.. 3 O.h COkCkhmINTralh7shG orfect:tew.o /14 (,
-}}