ML19220A250

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Background Matl on NRC Actions Since TMI Accident Re B&W Reactors.Includes Status Summary,Ie Actions,Ie Bulletin 79-05 & Info on Generic Review Task Group
ML19220A250
Person / Time
Site: Crane Constellation icon.png
Issue date: 04/04/1979
From:
NRC COMMISSION (OCM)
To:
NRC COMMISSION (OCM)
References
NUDOCS 7904170108
Download: ML19220A250 (23)
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Text

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.....'.. ;} -Q. .:/ / /_ BACKGROUD MATERIAL ON NRC ACTIONS RELATED TO B&W REACTORS SINCE THE THREE MILE ISLAND ACCIDENT P4 tdF - Su=:r.ary of Status of B&W Reactors. - Inspection & Enforcement Actions - I&E Bulletin 79-05 - Establishment of Task Group on Generic Review @) 7904170 log (v-(" o o). n1 ta u .~ -

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a D.. C-r r ? r I .l' 4 P l I t I. s I ATTACHMENT 2

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.w 4 [,. Office of Inspection and Enforcc~.ent Accions at Sabccck and 'Jilccx Cesigned Operating plants 1 The following acticns and instructicns have been placed in effect by the Office cf Inspection an'd Enforcement as of April 4, 1979: 1. The NRC Regional Offices prcvided ccpies of Preliminary Hotificaticas to licensees with operating plants so that iicensees would be aware of informatica concerning the accident. As subsequent Preliminary Nei.ifications are issued, these are promptly transmitted. 2. Inspectors have been assigned to each site with oper'ating Sabcc..k and Hilcox designed nuclear power plants. Resiient inspecters already had been assigned to two cf the five sites -- Arkansas Nuclear 1 and Oconee 1, 2, 'd 3. However, the resident inspector of Arkansas Nuclear 1 was being replaced because of prerotion and the inspector at Oconee was assisting at the Thr2e Mile Island accident. Inspectors were dispatched by Monday, April 1,1979, so that all five sites were provided g with resident-type 'nspectica coverage. 3. ILE Bulletin 79-05 was issued. Tnis bulletin was transmitted by telecopier frc:n the Regienai Offices to four of the sites (for the fifth, trans.hissicn trcebie was experienced -- it was hand-carried to the licensee). Regional manager.ent and supervisero discussed the Bulletin by telephone with licensee canacemer.t. <;g.1HD r., m-a W I

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2 4. A Temporary Instructica has been prepared cutlining the inspectors' duties at these plants. The instructions place requirem=nts on the inspector to perfcm the~ dutic-s specified in the Temporary Instruction and assume duties equivalent to assigned resident inspectors. 5. The inspectcrs are. required to assure that licensees are g fulfilling the provisions of the tiRC Bulletin at these plants. Inspectors also will assure that licensees are aware, insofar as is p racticab.l e, o r,uhe de ta i,t s or tn.e i h ree t,a. l e. l a n,e acc7 cent.- d G O 9 -1 O A ' (' O . Y .i ~ %W..,. N"OZ-M>TiF6' -,' 7 2pWJa>;Ji'-~-l' Tys' mym-rmwq~ms_wmeme m a ...c+:Amw:w.so.m : - O *dWM_ U7 ' -,.-m~ ~ .-f[-MC. ;C, % C[N-WOzi'ifl_' CATS.'lw~f '7 .. m R,$ 5 E T,.E' ~ W 5='> W M.%. R, 5. 5 )5lS,.~' $.,' $. m ~ '55 . ~% 2. * ' ~ ?' e.',==- ~b ^: ', ~ . M2 ~;f;' r j7:~3..iM. ::.-a,W-64:%' ?R ' M;M.. ~. f. 'ir ; ~,.=.., ,,.n -- - - j,M+"-:r-&.x '-~%-:=c ~ : " --:7 4. s...,W..?'5..MCS*$~,ffr' M;.=. [.,S$.,,.,5.,Y ?. y'. '.l. ~ WMW+'1EWV?R:- q-.. @ % P fi. 2.~d.!?;

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+t u, 9 8 r' t d ll L N Ej 5J tv tl 1 3, ft MD I L ATTACHMENT 3 l' l 0 e f}IT$Ik#I f.r:1 i s..

h l' ?RC ISSUES SULLETD; -., i...- 3.-,;.r Re ul a to ry Cc 7ission today has issued an Of fice of Insp:ction u in. u-c,,,; gnf 3,-cenant Eulletin regarding the i!cclear Incident at the Three tille 3..,,i reector. This bulletin is being.sent to all utilities with a.

p.,.~-t. and Wilcox pressurizac., wa er reac er, the supplier of Ine thraa t

u .v i ile.Isla :d Unit 2 reactor. These utilities are being provided early infor.:etica and assessment of the incident and are being asked ^ to ir.z.e-g eintely reitiew their facilities and precedures in light of the incid2nt ~ to nreclude a similar event. A Formal response to the !!RC i.s.requira-1 ~ within ten days.' This ser.e bulletin is being provided to all other po'.-rer m r.a. tor licensees and constructica per.,it holders in the country for 1 a :, ., t.....m,,., In a related action, the I!?.C has dispatched an inspectcr to every licensed site with a Sebcock and Wilcox reactor. These insoectors s;ill functica in a similar fashion to the resident reacter inspectors who era. being assigned en a regular basis to'all cperating recctor sites around the country, iney snll conduct inspections of ell aspects of the facility cperations in addition to the routine inspection progra perforced by SP2cialists in the I!RC's regional offices. They -zill be residing ne: c the site and, crk on a full-time basis at Gleir cssicmd sites. ?. - C g.

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Ap ril 1, 1,:/> %.s.. t.g,q.3.,r. ;00:-; FOR:

8. H. Crier, D,irector, Region I J. P. O'Reilly, Director, Region II J. G. Keppler, Director, Region III K. V. Seyfrit, Director, Regics IV

/ ~R. H. Engelkca, Director, Region V FRO::: florman C. Moseley, Director, Division cf Reactor Operaticas Inspection, OIE

SUBJECT:

IE BULLETIM 79-05, HUCLEAR IHCIDENT AT ThREE MILE 1 ISLAND f The subject IE Sulletin should be dispatched for action by April 2, [15@,to all SEi.' power reactor facilities with an operating license. Subject. bulletin and enclosures sh:.uld also be dispatched for inforc. tion , to cl,i otner cc. er rea'c,cor Tacilities with an o.ceratina lictnse and to .11 po :er reacter construction permit holders. ...y The ce;:t of the E'.;11etin, Enclosure 2 cnd draft letters to the licensea m ,tre enctosec Tcr Inis purpose, encicsure m unica.consts.s or Ine.. o,. i..,..i n 31,3, i.. =m. i.-, u. s,., s %. '>d_ be a M_ =_4 'c" tho. r'cion". 4 u ue 1., c.,..,....., : u v 3 s office. The letters to the licensee make the commitr.2nt to forward the continuing Preliminary l'otificaticas of the incident, These should be forwarded as they are received. /' / /Gn t -- ./, -

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n Norman C. Moseley. Director Divisicn or..eactor Operations o Inscectica O r... rice or inspac.ica cnm4 enrcrceman,u. z.

Enclosures:

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1. eus~ w.-

u na uui a to BG'e' Licensees 2. Drcf t Transmittal Letter to all other pow 2r ~ .,:. 1 u.._, 3 - 4 _ iu 3. IE Bulletin l'o. 79-05 c,. .c., - 1.,.2 m,._. 9, e o cp, ~m. 1.,. u.., 1 t n .+.- , u,, a....i-u. C. .d r,.p c,c r i c,;, 1,. f Cr _ ") ^< 1.W. J r-w. '.)* 4 '.ll f

hd;.g Tetter to C&W p'c.ter reacto'r facilities with ca op3 rating liter.se) IE Eulletin l'o. 79-05 Addracsce: Enclosed is IE Gulletin No. 79-05, which requiras action by you with regard lc your pc'..ler reactor facility (ies) with an operating.licease ot-a' ccastruction perait. Should you have any questions regarding this Sulletin or the actions t.ais cirice. required by you, please con, tac,u Sincerely, ~ Signature (Regional Director) Er.cl o sures : 1. IE Sulletin Go. 79-05 and Encicsures 2. List of IE Eulletins issued in the past 12 c.onths s O q e

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. (Orc.f t letter to all pc.;2r reacter facilities with cn operating liccase ~ l of-c. construction P2rdit) i IE Bulletin No. 79-05 t Ad ressco: J f The er.clcsed Eullatin 79-05 is fantarded to you for inforc.atica. No t ritten respcase is required. If you desire additional information' regcrding this catter, please contact this office. The Preliminary i:otification of the subject incident (Enclcsure 1) will continue to ba isq{yac. pe riog1 ca3 3y. ty:ese w13 3 ya vorwar,_ec, to you.as tney are issu:g. Sincerely, ( Sigatture (Rc;ianal Director) Enclestres: 1. IE Eulletin No. 79-05 cnd Enclosures 2. List of IE Sulletins ($) issued in the past 12 m.cnths e ( 4*

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, w r..,,,.. : n. 3. 79-05 Igril 1, 1979 u. Paga 2 of 3 k 1. P.eccpition of the possibility of forcing voids in the pricary i a. E coolani, system large enough to comprcaise the core cooling ) cccabil i ty-r,! Operator action required to prevent the formation at such b. voids. Operator actica recuired to ensure continued core cooling in c. ~ 7 the event that such voids are formed. g f 4. P.eview t.he acticas requested by the operating precedures and the training instructions to assure that operators do not override autenatic 4 actions of engineered safety features viithout sufficient cause for , f. coinc so. all safety related valve positions and positioning require- '5. P.e vi e.? r.ents to assure that engineered safety features and related equip-rc.2nt such as the auxiliary feedwater systen, can perfora their .n zu intended functions. Also revie.: related procedures, such as those or nintenance ana restir.g, to assure t.nat such valves arc returned I .c t.asir correc,u positions Toi,.cwing necessary manipulations. c t e 5. P.?vieu your operating modes and nrccedures for all systems designed to trar. ster potentially radicactive gases and Ticuids out of the. co n a1.....a. ;. Lo assure..unat undesirau, pumping or racloac Tve la.c,u T c,.s u and gases will not occur inadvertently. ~ @ In particular assure that such an occurrence would not be caused by the resetting of engineered safety features instrumentation. List all such systems and indicate: a. Whether interlocks exist to prevent transfer when high radiation ino,ication e.xis s _ and, c ,b. 1:hei.her such cystems are isolated by the containment isolation si gnal. ~ 7. Review your prompt reporting pracedures for URC notificatio:1 to .. assure very early notificatica of sericus events. r N.,c detailed results of these revie.-is shall be submitttd within ten J'Q rece i p c 0 7,thi s ;u,il c_ t. l a. 3 W, O ?.y $ C,:. T.n C u q d s

'e n F. !n i'o. 79 -05 f pril 1,1979 .d -,. 7 t. Page or 3 P.m -ts should be subm.itted to the Director of the appropriate ilRC F.[. ic. i Office end a copy should be forwarded to the l'?.C Office of Ini.:'rction and Enforce..ent, Division of ?.ccctor Construction Inspection, Uns hi.-.3 en, D.C. 20555. t For all other cperating reactcE.- or reactors under construction, tiiis Bulletin.is for inforcation purposes and no report is requested. ) Acproved by GAO, B180225 (R0072); ciearance ex.cires 7 '31-80. Approval

tras civen under e blanket clearance specifically for identi'ied generic p robl eas.

9 g ~ g e e e e T 9 af

i a ,3 :' r. Enclosure .....,,..,. ;:o, 7 9 -0 3 PUSC 1 0-3 f; ii 1, 1979 LISTIi!G OF IE BULLETit:5 t ISSUED Iii LAST TUELVE i:0:iTHS F Culle;in Subject Date Issued Issued To t i.o. 73-c.5 . Malfunctioning of 4/14/78 A.ll Po.-ter Reactor Circuit Breaker Facilities iith an. Aur.iliary Contact OL or.CP Mech anis.m.-General V,cdel CP,105X 73-05 Cefective Cutler-5/31/78 Ali Pc::er. Reactor Hamer, Type M Relays facilities '-tith an 3g liith DC Coils OL or CP ) 70-07 Protection' afforded 6/ 12/78 All Power Reactor by Air-Line Respirators Facilities with an y and supplicd-Air Hoods OL, all class E and. F j Research Reactors riith en OL, all Fuel Cycle f ~ 0 Facil-ities uith an OL, and all Priority 1 Material Licensees i 73-03 Radiation Levels fraa 6/ 12/78 All Pov:er and i Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Element s transfer tube and w s an OL. 73-09 B'.:R Dryaell Leakage 6/14/79 All BHR Power Paths Associated with - Reactor Facilities Inadequate Dry. ell with an CL cr CP Closures 73-10 Sergen-Paterson 6/27/78 All B"' o"'I' Reactor Facilities Hydraulic Shoch Suppressor Accumulator with an OL or CP i Spring Coils

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.I culietin !!c. 79-05 Enclosure
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1., 1c79 Page 2 of 3 r

ss LISTING OF IE Bl.'LLETI::S ISSUED Ill LAST TUEL'!E MO:liHS Eulietin Subject Date Issued Issued To Ilo. 78-11 Examination of Mark I 7/21/78 BER Pceter Reactor F> 111 ies Tor Ccatainment _ torus c Welds . tion : Peach Sottom 2 and 3, Quad. Cities 1 and 2, Hatch 1, Monti-cello and Verm:nt ' Yankee g ~ 78-12 Atypical Wald i'ateriai 9/29/78 All Fov:er Reactor' in <.eactor Pressure racTl1 aes uit,a en Vessel Weids OL or CP 78-12 A Aty.cical Weld Material 11/2?/78 All PC? er Reactor in Reactor Pressure Facilities :ith an Vessel Weids CL or CP ~ 78-125 Atypical Weld Material 3/19/79 All Pov:er R2 actor in Reector Pressure Facilities uith an Vessel Helds OL or CP 7%'3 Failures In Source :-:aads 10/27/78 All general and specific licensees cf :'ay-Ray, Inc., Gauges Model s 7050, 70503, 7051, with the subject 70313, 7000, 70503, 7051 Kay-Rey, Inc. ar.d 70518 gauges 78-16 Deterioration of Buna-M 12/19/78 Ali GE S'.!.1 facilities Ccaponents In ASCO with an CL cr C? Solencids 79-01 nvironrc. ental Qualifica - 2/C/79 All ?c,;er Reactor tica o f Class IE Equip. ant Facilitics with an CL cr CP .:) .n m e)- s,

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.,,c79 Pcga 2 ci 3 t

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r. i 6. LISTING OF IE SUt.LETU:5 ISS'JE0 IN LAST TUELVE MC.'iTHS P i Euli e tin Subject Date Issued Issued To Mo. 78.11 Exa:aination of Mark I 7/21/78 B'.-lR Pctier Reactor Centainment Torus Facilities for Welds action: Peach I Sotto:a 2 and 3, Quad. Cities 1 and 2, Hatch 1, Monti-cello and Yerment .,,an,cee s 0-78-12 Atypical Held Material 9/29/78 All Pot:er Reacter-in Reactor Pressure Facilities ;;ith an Vessel Weids CL or CP }.... 78-12R Atypical Weld Material 11/24/73 All Po'cler Reactor in Reactor Pressure Facilities.:ith an Yassel Helds GL or CP 73-122 .stypical Held Material 3/19/79 All Power Reactor in Reactor Pressure Facilities with cn Vessel Helds CL or CP 7*-13 Failures In Scurce Heads 10/27/78 All general and h of Kay-Ray, Inc., Gauges specific licensees Model s 7050, 70508, 7051, with the subject 70518, 7060, 7C503, 70G1 Kay-Ray, Inc. gauges and 70513 78-14 Deterioration of Buna-N 12/19/78 All GE 5'.a facilities Cetponents In ASCO with cn CL cr CP Solenoids 79-01 Environmental Qualifica-2/S/79 All Pc.:er Reactor tion of Class IE Ecuipcent Facilitics uith en CL cr CP .-}

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~3CR'.' 3. TION TO 1.ICESSIS'., .~S. ER9T <yRO';I r.*t2*.0:U'iUF.4 ENTITI.ED "CG5VEYING E,' 1: 3 C.*303 - D.*.VIS-3ISSE UMITS 2 6 3 ASD MIDU,1D m:ITS 1 & 2 D.m. ~ D it 'j .1.,, 9, : :,.0., J. S. Cn-5:.. :.: 7, 5 ; 2 c.-... . / _ 10 a.e. c. c J.. s,,..: c,, . i :, Inspection end Inforcenent p. aper t 50-345/75-05 dcct cated that 3. pressurizer level had gone of f scale f or ac. o. rc:.: irately five . cinut.s during the Nove:b...cr 29, 1977 loss of effsite power event. Wre are ser.2 indications th;c ethe: BU.? plants cay have prob- ."-m,.3",._a... _ c.->- _ _..- - s _ c. c u - '-_..o, i 3 p.assu ' =__ 1 c... s.- . m _'.. _' T-In addition, under certain conditions such as less of f acducter .o 100% power with the reactor ccolant pumps'runnin-the pres-a atscrir.cr nay void completely. A special analysis has baan per-forned concerning this event. This analysis is attached. as -nC,osura,-. DEC2Use a: pressurizer,cVe, C21CCinanCe prop- -, _,.c. ~. 'c'"' e u s.~..'. _ 3 - c n_ =_ w. s i. %.. n s.'... A.. e, o-t r. =. v = s s e. _ =..... c., Also noted during the event was the f act th a t Tcold vent off- . o - e d ~ %.. s s - h.. n-n.: n ) ?.h o r '. T,.. ->->_usC,.., 4u 4 og s u-s .) -c \\' 1 c .a -1 .c c C u s -t ns ..w,5. ..a ..1 C.. ,. r,. 4_ w o 0_ s. Js .ie_,<- o i ess t.ic.. l a "t en. 'e n..~ sw er- _.. w s. .w .o .s

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tacir eper.ional.linits only uring no 21, operating conditions, j Cooldown transients > such as less of effsite power sad loss of feed -

. 1.ater, sancti'=s.esu'u 4_.. o, 3-'-f p =ss. c -..d-vo l u...* e 6. '. e n. e., - h.. - k u 5 <,..,, a..s.. c a b '.1:..ty o r O.n:.s systen to centrol. A na analyses or-2, s ar.d c,::ctrence with such transients show, however, that they can be j ...s~_.u.-

m., t. _e - h o u.,_. compronts,.ng tna sa:cty c: tna reactor.

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.6'.. r- - 'c .Ihd 'Nf cI f analysis for P. Orc SOVOrc CColdM.-' t rC n s i c h.t s, such n'J the lo s s. e,r <eca, c_ e. m-.., 4, < c., ~,e t w.... s ne-.. _- o_. v a, e, c, ~,. e c m_- c. a, c -j t m d, to lec's than the s) sten volume exclusive Of the pressuri:cr. D u rin e.> suca .n eecnt, the emptying Of the pressuri:cr eculd be follOved c' y-i presare mduc: ion belev the scturation point and the forration of . s:c l..'. ecids throughout nuch Of the primary syc:cm. This would not i rcc' ic in th2 loss Of core cOOlin, beczuse the voids would be disperca C 's ' ' ' 1

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??UcLEr,S REGULi, TORY COMM15s!GN 6 Q n, usm.scTc.s. o. c. :ss ,j .5

a. w' v './.;:.;-

w-7t.C .~ g ,e npril 2,19,, v /> .p s,,,< MEh0?A?iOUM FOR: Edsca G. Case, Deputy Director, Office of liuclear Reactor Regulation FROM: D. 9.. DaYis, Chief, Syst=J.s Evaluations Progt Branch, COR, liRR SU3 JECT: TASX GE00? ON GE?iE:.IC REVIFd 0F FEED'.GTER T?AtiSIEtti IN B5'd DESIG??ED REACT 0?.5 As we discussed, a task grcup has been establisned tc avaluat: Q the generic implicatiens of feeciwater trar.sients in EaN desic: reac:crs. The Trembers and their charter are set forth in the encl osura. .t.n evaluation of the task group's findings and an; recerandations sh:uid be available in about ten days. L fM D. K. Davis ~, thisf. Systec:s ~ EvaTuations Progra:~. Branch

Enclosure:

Task group -. t ar., c,r.arter I1s cc: HRR Divis'en Directors , HPS. A/Ds R. _C - 4 u. a..1 :s 1 u8, T. t..5 3 G. Laines, PS3 Z. Pcsztoczy, AB. A. Oxfurth, IE P. Check, R53

5. Israel 1

7 a,t) 01 y. e. ~ ~. O

TASK GF.00? ON GDiE?!C F.EVIEW OF FEED'.iATER TPJJism;73 i IN B&W P.EACTG?,5 [ s e Mechers: S. Israel, Group Leader j P. Check, RS3 i R. Satterfield, IC55 6 G. Lainas, PSS ? Z. Roszteczy, AB F A. Oxfurth, IE I 'l Charter: Given the operating experience with feedwater transients i in cperating El'.4 desigr.ad reactcrs, assess whether reactcr and piant systems at these plants provide adequate protectica frc= design i basis feedwater transients. This assessment shculd re-cenfir= 1 whether these plant designs meet the requirements of MF.C regulations, using appropriate staff guidelines for acceptable means cf resting the regulations. This should include an evaluation of the safety margins cf these plant designs to assure that scacified acceptable fuel desigm limits are nct exceeded as a result of feedwater transients. e 8 G B e / I = 4 t I i a e I s 1 I I-i , y 7., a. I I t

y. IE Sull' tin i:o. 79-05 Enclosure e Page 3 of 3 . April 1, 1979 [. LISTIi!G OF IE GULLETINS ISSUED IU LAST THELVE MO::THS r Eulletin Subject Date Issuad Issued To n flo. 79-02 Pipe Support Base Plate 3/2/79 All Power Reactor Designs Using Concrete Facilities with an i ~ Expansion Anchor Scits OL or CP 79-03 Longitudinal Held Defects 3/12/79 All Po.-ler Reactor In ASME SA-312 Type 304 Facilities with an m; Stainless Steel Pipe Spools OL or CP U"' Manufactured By Youngstown Helding.and Engineering Co. 79-04 Incorrect Ueights for 3/30/79 All Po. er Reactor Swing Check Vaives Facilities wita an Manufactured by Velan OL or CP Engineering Corporation l l 9 e %s .}}

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