ML20059C764

Summary of 394th ACRS Meeting on 930211-13 in Bethesda,Md Re Key Policy Issues for Advanced Reactor Designs,Schedules for NRC Review of Proposed Reactor Designs & Reactor Operating Experience on Restart of FitzPatrick Nuclear Plant

ML20059C764
Person / Time
Site:	FitzPatrick
Issue date:	05/07/1993
From:	Shewmon P Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2868, NUDOCS 9311020009
Download: ML20059C764 (43)

Text

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g f* R fpp /gMM3 Fj Certified By: J Date Issued: 04/27/93 P. Shewmon - 05/07/93 i

TABLE OF CONTENTS 4 l MINUTES OF THE 394TH ACRS MEETING

! February 11-13, 1993 l l

I. Chairman's Report................................. 1 II. Key Policy Issues for Advanced Reactor Designs.... 1 III. Schedules for the NRC Review of Proposed Reactor Designs................................... 5 IV. Reactor Operating Experience on Restart of the Fi tzPatrick Nucl ear Pl ant. . . . . . . . . . . . . . . . . . . . . . . . . 7 V. NRC Regul atory Review Group. . . . . . . . . . . . . . . . . . . . . . . 8 VI. Mul tipl e Systems Response Program. . . . . . . . . . . . . . . . . 9 i

VII. Atomic Safety and Licensing Board Panel........... 10 VIII. Briefing on Recent Changes to the Regulations I on the Conduct of Government Employees........... 11 IX. ACRS Subcommittee Activities...................... 12 X. Future ACRS Activities............................ 13 XI. Research on Organizational Factors................ 14 XII. Reconciliation of ACRS Comments and Re come nd a t i on s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 XIII. Miscellaneous

• Proposed Rule - Exemption from Criticality Monitoring for Unirradiated Fuel at Light Water Reactors................................ 18

• ACNW Review of Interim On-Site Storage of Low-Level Waste Operations................... 18 XIV. Summary / List of Follow-up Matters................. 18 0

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TABLE OF CONTENTS ,

MINUTES OF THE 394TH ACRS MEETING l FEBRUARY 11-13, 1993  !

i XV. Executive Session

- Reports.......................................... 19

• Memorandum....................................... 19 Supplement - Proprietary - Official Use Only isu m onrut m u ro - ro A EX(b W H

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iii APPENDICES MINUTES OF THE 394TH ACRS MEETING FEBRUARY 11-13, 1993

1. Attendees -

II. Future Agenda III. Future Subcommittee Activities IV. List of Documents Provided to the Committee 5

l l

i i

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, i Federal Regfx.r / Vol. 58, No.16 / Wednesday, Janua., 27, 1993 / Notices cp/pt.q d 6315 N4.ddCCtrQ

[

following proposal for b collecilon of 3019.O!! ice of Management and Budget, published in the Ihderal Register on Wathington, DC 20503. Demmber 23,1992.

information under the provisions of the Paperwork Reduction Act of 1980 (44 Comments can also be submitted by Thursday, February 21.1991 U.S.C chapter 35).7. ; 7'* " telepli.me at (202) 3c5-3084.

2. Type of submission, new. revision, ne NRCClearance OfSwr is Brenda a:30 a.m.-8:45 as: Opening or extension:New (Expedited OMB Jo. Shelton,(301) 492-8132. Remarb by ACRS Chaumon (Open)-

review requested within 30 days). Dated at Bethesda, Marytand, this 19th day "Ito ACRS Chairman will maka opening of January 1993. ~ t. remarb regarding conduct of the

2. The title of the information meeting and comment brie 0y regarding colicction: NRC Survey: " Assessment of - For the Nuclear Re6statory Commtalon.

the NRC Operator Licensing Program.** Items of current interest. N Committee Gerau F. Cronined. will discuss priorities for preparation of and follow-up interview, I d#I""#**

J. Theform numberif applicable:Not % [*^ reports during this session. .

or

. opplicable. .,.w y .

• b 'f*- I 8:45a a -22 c A :KeyPolicyIssues

[FR Doc. 93-1946 Fued 1,28-63: 3:45 sm]

, 4. How often the collection is . , - _

,:, ' forPrupplication D&gns (Open}- %

v required: Oue time for the initial surwy ..n , . , - - ' '

Committee will review and comment on

. . ' and one time for a follow-u interview .

y,,. .n. s -e. " key Ucyissues identiSed by b NRC with a ansan percentage of surny Advisory Committee on t+xteer for resolution with rwpect to -

,,_,,_, advanced reactor designs such u the respondenta.

5. Whg will kej.:sked to report:A, m Weste;Weting

.e . e ....@2m rr *"~ c Mif!CR, PIUS, PFJSM. sud CANDU-3

. sample of nuclear industry personne : l , W soth the Advisory Representatives of the NRC staff, the . -

W aste M r ind* mambers of the Fa.' -hat ~. tofEnergy andtheinduitr/;~

L, Pa' *ne Operster Society (PROS),the ^ ; C-m*aa en .aMla(to gp' be held

, , Wednesday and ,.,.y, Nndaer Menagement Resourm Cocod! ,'January 'It 27.and 28,1993,8:30 .

22 u-22:45 na: Schedules.ofNRC J- ~! (NUMARQ, and the Iristitute ice' .4 " ~'- am n I 6 p.m., room P-110. T920 . Redew Proposed A6'anced Reactor, .

' Nw4adPmne' Operations (INPO): as " ~ Norfolk Ayunus, Bethoeda.hD has been De=sns H m en-nitm % -

' t tw His a crom:eedlon'of tocattyS rwindesJonows.gw.9:be Portions of thismeeting may . hear a brie by and hold M-==4==

per=-nailMM

'- dr.# with.rspresentatitis of theNRCitsf[on' 1 4 :- ar c6.An sstGEthe . V*hiunbe[o[f f

• E' closed topubuc att=ewtanna if deemed

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Y2 1 -hiddir=ada t"i'"

designs. .

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7. An estimate of the 106:1numberof source (5 U.S.C.552b(cK4):10 CFR 22:45 pa-2:25p.m.rF2tx?attkki y

• hours needed annually to completa the 2.790(dX21).tenaad= %t relates .

. solely to theinternal parerrmal rules NuclearPcmarPkzat(Open)-b A.

. ' , - sequmenent arroquest:54 hours De Committee wiH bear a brisang and hold minutaa.per surwy and one hour per and pr**ma of the ACNW D U.S.C...

restart of the. '_ O intarriew);W mi ' %,_' 552b(cX2)).1 nd inbrmad= a cieerfy the reisese discussions p4aar p. ant foUowing of which wonktrepresent Fitzpatrick mv

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8. An'indkxzdon of whethersection - " a +=aAad shutdown for plant and v,[i .

23504(h); Pub /f,9642.2 a . unw.u-a. Invasion of personal 1

.pplies Nat '

( U.S.C.552b(cX6]). bee or!=ah*==1 changes. Representatins .

A <

.' . a ..gh.; esadons.willbe. devoted tomeeting with of the licensee and of the NRC ets.ff willp d . Mfj ppbcable.WTG sh ' $R

1. k f.qlnfervW v-R- rabmy/s'with(CE)anshirslucta*

and foDow-cp ".'d * % Nathal RadiolopealProto: tion a asz:iple of arrv4antY.' ~

privacy 2:25pm 5 participate, as appropriate.hWe e 030p.m::NHCSofu!5tery 7 e-

@ ina; f '.nl na part ofinW;W. aBoard h aa' *of timiMaN=d=' to discuse Redew Group (Openb'Iw gw evnb nnbf theNRC hadag # 41 Mea?nov$dedjiytheBoardnan,he wiH disms & ahigh,3ent proposed charfairks'M - x .

W program.4heprimary of the : b'+vp wastaM Aay and ANW end activities of the NRC RegulatoryW 9 survey ers'ta: 9u%Mee-nw.t .h'ro f5ceh 4 ands - = =' *AH AaI Review Group.h purpose o(this E-4

Notles of thismeetingwas group win be to crevb1 d e i WM'Ef

.hl)Ida-tiFy W w.u.nm,probleens r a.+.rrytwithCi 1% c;rp.r V 9 in thefederaltapeteron % ,~ @afn anddiscipl6d rede# .

' l' ef5deog(and m*"maamd of . .g Januaryt23983 D8FR.3982); AH of power rearsnr regninths and related N ,,,c.. ttams iAu.% to this' remain sad 9 t C

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.e' operstar GM rogram'end p Alama as . , the samaas previously pnM =

NRC process,prar implementation rW*ma%,W ~.

p *,'ne dotarmha arbethir thedse  :*- m Repementauva of the NRCitaff thd rwunof a r

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) ' (2)1deatify'llie %g and 3 [.o,gdgesp,$t,ha w;. d. 'mlehe;" b f dg ." the industry wiD participate;eeMM*Df -

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M f!V nspeedernhi= Mad h Tat 't" h. h ' 4,n_ Partions of this sessiostufQsciandP to discuss in" . > thetelenos ofah 70 i

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' .Of A 5* *.r+ wa'30 and tastitof tQQmf , widch would represent a .

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unwarrsnted tonelon of Pd"CT' ' 4S.n % $-

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and cuestions

.t-shadidSe~% sasagnardeartilbandEinsatina 5 p.m.-3:30 on P K G i= k ACRS Reports (Open)-The tv *=%

• j' will dIarms reportsregard!bgk ,

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-@:M fdirected to the Ot4B reviewerJRonaldW Pobruhryttt-13.:1968dn Betbooda r  :.1 hems consid duringthispp. Econ P-1to.

3 k,M!nsk.Of5asofInformaticaehd Ach7220NoriSZkMqntss: Regulatory Affairs i ?a f f. .

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, i RSW Sais rederd Registes / Vol. 58, No. ItN/Medriekday', Janurtry 27,'1993 / Notfeed Representativer of the HRC staff wil) -

- Deed:Jeourry2L NSI -

Friday,JWsry n, N John C fleytr _ .

partidpate, as appmpriate.. ,

' 8:30 a.ni.-!O o.m.:Rbla leSystem 22 Noon--1220fr.ar.:hetaseRTatfort of ' Adrincey rum uma m-~.a agia,,...

nses (Opac se [FR Dor,. SM650 Pund 1-26% 84 emi Cbmmittee ^ heer a briefing by and ACRS Comaamtr ard ' - ' .

Recomunendedord pren)- ' time . . ,,, o watfree of ses bbid the NRCstaff discrerkmsgtwith wbr statursecubed of thefromCommittee theMRC will esa discous skfI'swtat for witfr the recommendstions made in ACRS .

p)tential . e safety issues fdentifred F'PDFt&, ReprGesOtmlhFe6 h$ the NEC stNff Of7tCE OfrTHE UNITEDSTITES iAthe e System Pw

• TRADEREMtE5ENTATTYE will partidpate, as approp"date, . '

U:30 PAA Fina '#" ~ ~ ' ' .

1M5 a.nekit.45 a.or. Afdmit-Safety Nedceof Estebilehmerd omspste abdLicensing NoenfPimeIActivi6er (Open)--m rmmdasa,wcN .

i mattats consideredbut aca cocupleted at ' Setnemert Penel Concorrkg U.S. .

(%Wemanittee and as time and. , , , Import Restrie5ene eMiditer l mymuntstfese of the Aroente safety sad previousavailability ofin tion permit.

j licenntng BoardPanel(ASU!P)will Procedures far b moduct ofand mmOmce of 6eMed 5ts's discuse saataats of mutud intevent, Trado Reptisentethe. j partid be ACRS seestinsprwere bcludmg b cmrent and ancicipated in the Federa15egleenr en . . m Notica.

c::tivities d the AtmaJc Safety and Pub October 16,1992 (57 FR.47494). In

• - r ic=whg, Board Ptnet 11a85 a ra-21.R)pm.r Preparation of ecmrdance with these pescedews ord.- scanWtnWOfEcs oftheUnited or wrloes seafsanmer mayIe y-" StatesTmde Representative (DSTE3 fa .

ACES Erpocss(Open)-h O-m*a. r ken *wh naf repeatsregarding by membemof thepublEtcrucortffags ' previdbg n* _ -

will discus *' d during this meeing.

tramecanaldere wiubeperndamd only deringtbsee' Statesnada r hmt E'H - rm n'et' OPen partiene of the rneetingwben a F:30pm.,7p.m.;Enefag on Recent has estaWhed a @dStates Chances to de Regula6ons on d, transcript is being beipt, and stues8 ens under b Unna Canada '

may be asked only by usersbers ofthe ConductofGo.enunent anplopes Commitnes,les counseRameniand see.fE V T,My Cansbrade MWAgreement to review (Openl--hrhmh win hear a Persons desirIngte make tsiel' sfstement" governingtheim"=b ofM '

bneEngby and hdd ifMa tma with . ACKS

reposenta5ns of the NECOfEcs of the should ncGfytbs tamperature (DHilmilkinto Puerto '

ExecuSve Ulmeser,Dr, 7,IArkksL Rico.

GeneralCounsef on b Impact on Ai.'RS as far isr adrance as ponct5cale se thes v,vni members regarding th implementstfon DATE8:%s pumet is currently scheddsd-of the recent OfEceofConrnment approprism arsa r-- 1 conbemade to issueits repces by Apr2 7, tan, to aDow the neesssary times during the Ethics government-wide chrmges to the meeting he such stelessenen. Des of sd3' PM PUWER IMSIKTON @NTEP.

reguMon ce thecondoet of nmuco picture, and televistan camerne Jeanne DavidsonJaaneimaa General goverraserd eerployees, during thts moedog may be finnited str ,g% %

JJ5p.ar.4:15 p.m r Resetrreft on Organise#endPactbrs (Open)--W s*lected pmtkxis of theLrueeGog as A h ands hikehI CommMew willhans e briefing and held determinedbytheChednussa.

a dGahI discussioneregarding NRC-sponsored k6 ai~ regudlagthetienebbesee Couned, US'IR 500 27a StroM -

aside be this puspose susy be obtained W-Wi= DC2050ti,Cm2I395-3132' ~

research on organizational facters, Reyeeemtstivesaf theNRCstaff andof by e yespeldtelephas em38 tothe

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theinduetrywin peticipata,as Acting ACES henr6so D6suctarprior to the meettn6.ha v6ser ad one pa=#ery - surruusspecurr tercennahmec As a reamte appmpriate6 that the schednio SurActs mesdngs . of retzady adopted respdsdans by time 5:15 pmA p.ar.:FuttueACRS Commonwealth of Puerto Rtcu, tJO Activiues40 pen} hCbmmitteewfil may be ed)ustedbythe Chainnan eso n"=a yto factbesteties scudocsof the r

milk fmm 'anada isseimagerpeemittad i discuss the repest of thePinnnMg and to be import =d inra Pausto Ricxa.

Paceduru Sdecocunittaeregssding meetio6 Personsrhw is met =M L sheschichectwillsthe Acitng ACR3' W G-oost of Camde bat-isosas proposed for consideration by the Executive Directorif such anschedattn6 requested the estaW!sinnent oft dispats full Committee. setdementpaid unda dietemre d 6e w uld resdtfametertrerrosaisoc*-

Satunfay,M*"TT f3,It93 Ihave determinedin a-% with United Statse.Cmeds Freehde 8:30 a.mA s a.nu Pw;muution of Subeaction 10(d) Public law 92481 Agreement 6:7 dhi,, whetherthe ACRS Reports (Open} b thWties that it is necessary to closa pardons of Commonwealth ofFoerto Rfai/r wtB discuss proposed Committee this meeting noted above to discuss measureis h-a.IAsst wfer the reporta m,wTwg I!sms considered information tfre release ofwhich wedd obligations of the United States arrdtr during this meedng, reprieunt a dearly unw d.d b Unihd Swas Ca radeFNo-hde 12 a.m.-22 Noorr-Activftfes ofACRS invseien of persond priveey per S Agreement.

Sumuudu.s(Open)--b CumWm., U.S.C. 5521(cKS). D* Penel w3Tocmduct itr will hearreports on and bold Further information regardingtopics Proczedmgn in acctedance with artfde discussionsof thestatusof ACKS to be, 'i*==ad whether Ge moeda IBM dSe edSta W Mame.

submmmh assignments,inchsding has been conce51ed as recebedaled e the condact ed Committee acifvities by Chairman's ruling arr requests Ibr the Trada schedMA--nant toissueits andisEnalreport cumm@ fry the Plann.tng and pmcedures opportunity to present osal statmenents April 7, MI.

Subcommittee, use of digital and the tisae aHotted cars be ebodned by a prepaid telephoneedito the Acting G3E M**"-

Instrumentation and control systems in Genem/CounamL i i nuclear power plants, the ABB -CH ACRS Executive Dlisctor.Dr,Jobcz7. ',

Larkins (tdephens Se1.-+sL451eh IFR Doc. 95-2003 FusM-m-SA e45 aml Systata 8% design, and pmeedures km L between & a.m. and4-39 pan.EST. se.aesa coer sem-na conductof ACRSbusinesa.

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[pa atog#'o, UNITED STATES y* ' 'n NUCLEAR REGULATORY COMMISSION 3 ADVISORY COMM11 TEE ON REACTOR SAFEGUARDS o W ASHINGTON, D C. 20555 5

• % ....4 February 5, 1993 SCHEDULE AND OUTLINE FOR DISCUSSION 394TH ACRS MEETING FEBRUARY 11-13, 1993 Thursday, February 11, 1993, Room P-110, 7920 Norfolk Avenue, Bethesdat M512

1) 8:30 -

8:45 A.M. Openina Remarks by ACRS Chairman (Open) 1.1) Opening statement (PGS/SD) 1.2) Items of Current Interest (PGS/JTL) 1.3) Priorities for preparation of ACRS reports (PGS/SD)

2) 8:45 -

11:00 A.M. Kev Policy Issues for Advanced Reactor (10:00-10:15: Break) Dcaians (Open) i TAB 2 -------- 2 .1 ) Discussion of key policy issues raised by the NRC staff applicable to the MHTGR, PIUS, PRISM, and CANDU 3 reactor designs (JEW /EGI) 2.2) Meeting with representatives of the NRC staff, the Department of Energy, and the nuclear industry, as appropriate 2.3) Discussion of Safety Goal Policy Implementation issues

3) 11:00 -

11:46 A.M. Schedules for the NRC Review of Proposed Reactor Desiang (Open) 3.1) Briefing by the NRC staff on the TAB 3 --------- current schedules for the review of proposed advanced reactor designs (CM/EGI) 11:45 -

12:45 P.M. LUNCH - 12:00 Noon: Showing of videotape in Room P-110 on the effects of Hurricane Andrew on the Turkey Point site (20 minutes)

2

4) 12:45 -

2:15 P.M. Reactor Operatina Exoerience (Open).

TAB 4 ------- 4.1) Briefing regarding the restart of the FitzPatrick nuclear plant following an extended shutdown for plant and organizational changes (JCC/PAB) 4.2) Discussion with representatives of the NRC staff and industry, as appropriate 2:15 -

2:30 P.M. Break

5) 2:30 -

4:30 P.M. NRC Reaulatory Review Groue (Open) 5.1) Briefing by the NRC staff TAB 5 -------- regarding the NRC staff's proposed Charter for and activities of the NRC Regulatory Review Group (HWL/MDH) 5.2) Discussion with representatives of the NRC staff, as appropriate

6) '430 -

5:00 P.M. Accointment of New Members (Open/ Closed) 6.1) Discuss qualifications of candidates proposed for appointment to the Committee (PGS/JTL)

(Note: Portions of this session will be closed, as appropriate, to discuss information the release of which would represent a clearly unwarrented invasion of personal privacy.)

7) 5:00 -

5:30 P.M. Discuss Procosed ACRS Reoorts (Open) 7.1) Proposed report on key Policy Issues for Advanced Reactors (JEW /EGI) 7.2) Proposed report on the activity of the NRC Regulatory Review Group (tentative) (HWL/MDH)

Friday, February 12, 1993. Room P-110, 7920 Norfolk Avenue, Bethesda, Md.

8) 8:30 -

10:00 A.M. Multiole System Resconses Procram (Open) 1 TAB 8 ------- 8.1) Briefing regarding the status of the NRC staff's work for dealing with the ,

potential generic safety issues  ;

identified in the Multiple System Responses Program (CM/DC) 8.2) Discussions with the NRC staff, as appropriate i'

10:00 -

10:15 A.M. Break I

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i t 4 3 ,

9) 10:15 -

11:45 A.M. Atomic Safety and Licensina Board Panel Activities (Open)

TAB 9 ------- 9.1) Briefing regarding the ;urrent and anticipated activities of the Atomic Safety and Licensing Board Panel (ASLBP) (PGS/MDH) 9.2) Discussions with representatives of the ASLBP, as appropriate

10) 11:45 -

12:30 P.M. Precaration of ACRS Reports (Open) 10.1) Discuss the scope and content of proposed ACRS reports on matters considered during this meeting 12:30 -

1:30 P.M. LUNCH - 12:45 P.M.: Showing of an ANL-produced videotape in Room P-110 on the 50th anniversary historical overview of the startup of CP-1 (20' minutes)

11) 1:30 -

3:00 P.M. Briefina on Recent Chances to the Reculations on the Conduct of Government Employees (Open) 11.1) Briefing by OGC regarding'the impact en ACRS members regarding the implementation of recent Office of Governnnnt Ethics government-wide changes to the regulations on the conduct of government employees (PGS/GRQ) 11.2) Discussion with representatives of OGC, as appropriate 3:00 -

3:15 P.M. BREAK

12) 3:15 -

5:15 P.M. Research on Orcanizational Factors (Open) 12.1) Briefing by the NRC staff on the TAB 12 ------- status of the NRC staff research on organizational factors (JCC/HA) 12.2) Discussion with representatives of the NRC staff and of the industry, as appropriate

13) 5:15 -

6:00 P.M. Future ACRS Activities (Open) 13.1) Discuss recommendations of the Planning and Procedures Submimmittee regarding items proposed for consideration by the Committee (PGS/RPS)

1 g

4 Saturday, February 13. 1993, Room P-110, 7920 Norfolk Avenue, Bethesda, Md. ,

14) 8:30 -

11:00 A.M. Preparation of ACRS Reports (Open) 14.1) Proposed report on key Policy Issues for Advanced Reactors (JEW /EGI) 14.2) Proposed report on the activities of the NRC Regulatory Review Group (Tentative) (HWL/MDH) 14.3) Proposed report on the status of the NRC research on organizational factors (JCC/HA)

15) 11:00 -

12:00 Noon ACRS Subcommittee Activities (Open) 15.1 Planning and Procedures Subcommittee (PGS/JTL) 15.2) Computers in Nuclear Power Plant Operations (HWL/DC)

16) 12:00 -

12:30 P.M. Reconciliation of ACRS Comments and Recommendations (Open) 16.1) Discuss replies from the NRC Executive Director for Operations regarding proposed reconciliation of ACRS comments and recommendations (PGS, et al./SD)

17) 12:30 -

1:00 P.M. Miscellaneous (Open) 17.1) Complete discussion of matters considered during this meeting and matters considered but not completed at previous meetings as time and availability of information permit.

I pm.%,

hh MINUTES OF 394TH ACRS MEETING FEBRUARY 11-13, 1933 C RI a g y- ,.

The 394th meeting of the Advisory Committee on Reactor Safeguards was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Md., on February 11-13, 1993. The purpose of this meeting was to discuss and take appropriate action on the items listed in the attached agenda. The entire meeting was open to public attendance, with the exception of a portion that dealt with the selection of new Committee members and other matters of a personal nature. There were no written statements nor requests for time to make oral statements from members of the public regarding the meeting.

A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room. (Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd., 1612 K Street, N.W., Washington, DC 20006.)

ATTENDEES ACRS Members: P. Shewmon (Chairman), J. E. Wilkins, (Vice Chairman), J. Carroll (Member at Large), I. Catton, P. Davis, H. Lewis, W. Lindblad, C. Michelson, T.

Kress, R. Seale, and C. J. Wylie.

I. CHAIRMAN'S REPORT (0 pen)

Note: Mr. Duraiswamy was the Designated Federal Official for this portion of the meeting.

Dr. Shewmon, ACRS Chairman, opened the meeting at 8:30 a.m. and mentioned the following matters:

• The agenda for this meeting.

• Noted that several members of the ACRS staff had been given awards.

= Mentioned a request for papers for a British Nuclear Energy Society meeting in May of 1994.

= A retirement party for Ray Fraley at the Officers Club at the Naval hospital following this days meeting.

II. KEY POLICY ISSUES FOR ADVANCED _R_[ ACTOR DESIGNS (0 pen)

Note: Mr. Igne was the Designated Federal Official for this portion of the meeting. ,

Dr. J. E. Wilkins, Chairman of the Advanced Reactors Subcommittee, stated that the purpose of this session was to continue the Committee's review of  !

the key policy issues identified by the staff for advanced reactor  !

designs. This session was devoted to the pre-applicants of the MHTGR, 1 PRISM, and CANDU reactor designs. No presentation was made on behalf of i the PIUS design.

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394th ACRS Minutes 2 Oraanizational Structure and CANDU 3 Status Mr. D. Hink, Vice President and General Manager of the Atomic Energy of -

Canada Limited (AECL) Technologies, provided an overview of the organization and current status of the pre-application review of the CANDU 3 design. AECL is owned by the government of Canada. It operates as a corporate entity, according to all of the business laws and business acts in the government, but all shares are held by the government of Canada.

Mr. Hink provided a brief history of the evolution of the CANDU reactor designs starting from the mid-1940s. Three of the top ten nuclear power plants worldwide in reactor performance were of the CANDU design.

AECL Technologies is reviewing the possibility of participation with EPRI in establishing a requirements definition program applicable to pressurized heavy water reactors. As part of launching the CANDU in the US, AECL Technologies is seeking a strong US partner (s) in order to put together a total CANDU design package.

Suppliers and subcontractors in Canada provi.de equipment and components for the CANDU design. The equipment and components are built to the Canadian Standards Association, Z-299, which is similar to US Standards.

Ultimately, with a US partner, suppliers and subcontractors will be sought from the US.

The present plan is that the CANDU 3 fuel will be all natural uranium.

During normal operation the void coefficient is negative; however, during some accident scenarios, when the normal liquid phase goes into the vapor phase, a positive reactivity component occurs that will be counteracted by other coefficients and the scram systems.

DOE Presentations Mr. Griffith, Director of the Office of Advanced Reactor Programs, discussed the DOE's positions on the policy issues statement, including the program plans and schedule for the advanced liquid metal-cooled reactor (ALMR), and the modular high-temperature gas-cooled reactor (MHTGR). He stated that the NRC safety policy for advanced reactors is workable and useful.

The DOE's schedule is driven by the Energy Policy Act of 1992, which requires three important top-level dates that DOE must meet, as follows:

= The first milestone date for the ALMR is September 30, 1996 - DOE must submit an application to the NRC for preliminary design approval of the standard plant.

The second date is September 30, 1998 - the DOE secretary must submit to Congress a recommendation to build a prototype demonstration of a plant for one or more of the ALMR technologies.

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. By December 31, 2010 - DOE must complete the R&D and demonstration to support the design of an advanced reactor that can be put on an electric utility grid.

GE Presentation on the Power Reactor Innovative Small Module (PRISM)

Desian The PRISM design is a compact liquid metal fast reactor. Nine reactor modules make up the power plant, with each module located in an underground silo. Metal fuel is used as opposed to oxide, with six control rods. Any one rod can shut the reactor down at any point in the fuel cycle. There are no pumps and the decay heat removal system is passive.

Mr. Hardy, General Electric, indicated that the staff's positions as stated in the policy issues are normally similar to what GE has been proposing, i.e., departure from current regulation should be considered from the performance based viewpoint, rather than a prescriptive based viewpoint. There is disagreement on the staff's position on the issue on control rooms, in that the staff recommends using current LWR regulations until a policy issue is developed for passive'LWRs. For the PRISM design it means a IE control room in a building designed to Category I Seismic standards, having both IE instrumentation controls and HVAC. The current PRISM control room design is not IE. Mr. Hardy stated that the staff should allow a performance-based viewpoint in the control room design.

In reply to a aestion by Dr. Shewmon, Mr. Hardy stated that hermetic seal welds are ust- at all penetrations. These can be cut and rewelded many times and mun be replaced periodically. These seals prevent air from entering the liquid metal systems.

In a reply to a question by Mr. Davis, Mr. Hardy stated that PRISM will be designed for 0.5 gs, but a domestic plant will be licensed to 0.3gs.

General Atomics (GA) Presentation on the MHTGR Concep1 Mr. Silady, General Atomics, noted that in addition to GA, Combustion Engineering, Bechtel, Stone & Webster, ORNL and Gas Cooled Reactor Associates are working on this program.

Mr. Silady believes that the advanced reactor policy, together with the safety goals, should provide the guidance for the key issues. The following are his comments for each of the eight key issues.

. Accident Evaluation - NRC guidance is satisfactory, but needs specific criteria.

. Source Term - NRC staff guidance is satisfactory, but needs more guidance on the treatment of uncertainty in bounding events.

. Containment - The concern here is the definition of a containment challenge, which is a new term that needs definition.

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Emeraency Plannina - The staff will require advance reactor designs to establish offsite emergency plans and provisions for periodic off-site drills. This is a problem since the calculated doses of the design results in doses that are far less than the protective action guides.

• Ooeratina and Staffino - NRC guidance is satisfactory.

• Residual Heat Removal - NRC guidance is satisfactory.

Control Room and Remote Shutdown - The NRC staff intends to apply current LWR regulations and guidance to the review of advanced reactor designs. They should not be applicable to a design where the operator is not needed to protect the public.

Safety Classification - The staff intends to apply current LWR regulations to classify systems, structures and components. The current classifications are very LWR specific, while the GA design puts the emphasis on risk-significant systems, structures and components.

NRC Presentations Pro.iect Comments. Mr. Pierson. NRR Mr. Pierson, stated that they intend to consider comments from the ACRS and pre-applicants, and possibly add an addendum or an appendix to the key issue policy paper, then they will issue the paper.

Some Thouahts on Usina Safety Goals. Dr. T. Murlev Dr. Murley, NRC staff, discussed safety goals and their role in the advanced reactor review process. He had the following personal comments:

The proposed designs are within the Commission policy on safety goal s.

The staff's reviews of advanced reactor designs are based on the defense-in-depth principal.

The designers and pre-applicants must show that their designs can accommodate a severe accident. The assertion that safety goals are met with a wide margin is an indication of satisfactory design features but that, by itself, is not adequate to make a finding that the plant is as safe as it has to be.

Dr. Murley stated that the quantitative health objective and the large release guideline are not compatible when compared on the same kind of basis. The health objective shows that the risk for an individual living near the plant is about one in a million per year. The design guidelines don't address individual risk but relate to core damage frequency.

Therefore, when one works from the health objectives (which are the safety

394th ACRS Minutes 5 goals) backwards to core damage frequency, the result is in the range of one in a hundred per reactor year. This, Dr. Murley stated, is the reason the staff has not made serious progress in implementing safety goals in the regulatory process.

Dr. Murley noted that on June 12, 1992, the safety goal policy statement was made to define an acceptable level of safety for the nuclear enterprise. If that statement means that we can accept a one in a hundred per reactor year core damage frequency (CDF), then it would indicate that we can have a core damage accident once a year without violating the health goals. He suggested that this is not acceptable and not a good regulatory posture. Dr. Lewis noted that this gap is due to the change in the definition, driven by conservatism, of core melt to assured core cooling. He said that If we went back to what was originally intended in the Rasmussen Report as core melt and not core damage, all of the numbers should fall into place, and there would be no problem.

In summary, Dr. Murley stated that after some very preliminary analysis, one finds a large difference between the safety goals and the large release guidelines.

In reply to questions by Dr. Shewmon on whether advanced reactors should be an order of magnitude safer than current plants, Dr. Murley stated i that, yes the EPRI guidelines have core damage frequency of one in ten thousand, but nonetheless, the staff should not enforce that through the regulatory process.

Conclusions The Committee provided a report to Chairman Selin commenting on the ten key issues that need policy direction from the Commission for proposed deviations from existing regulations pertaining to the advanced reactor and CANDU designs.

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III. SCHEDULES FOR THE NRC REVIEW 0F PROPOSED REACTOR DESIGNS (0 pen) i Note: Mr. Igne was the Designated Federal Official for this portion of the meeting.

Mr. Crutchfield, NRC staff, stated the staff is in the process of reevaluating the schedules. GE owes the staff a submittal that should complete their safety evaluation, SSAR and final ITAAC. The schedule process will be proposed to the Commission soon.

In reply to a question by Mr. Michelson on GE's target completion date, Mr. Crutchfield stated that GE is evaluating its schedule with the DOE.

The staff expects input from GE soon. Mr. Michelson reminded the staff that the ACRS has not seen much of the detailed information that has been promised. Mr. Crutchfield acknowledged this comment and said that the staff will notify the Committee when it receives the schedule from GE.

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394th ACRS Mingin 6 Mr. Crutchfield mentioned that Combustion Engineering is aggressively resolving open issues on their Systems 80+ design submittal as they are being received from the staff. The difference in time in the review process between System 80+ and ABWR has been dramatically reduced, to the point that the Systems 80+ review may pull ahead of the ABWR review.

Mr. Crutchfield said that with regard to the status of the EPRI Passive Plant document. EPRI and the staff have agreed on how the remaining problems will be resolved. The SER for the passive issues has been published, with only one key passive issue on the regulatory treatment of non-safety issues as still being open. Senior NRC management from NRC discussed this issue with EPRI and a process is now in place to resolve this issue.

The AP600 application has been docketed and the staff has begun its review process. Approximately 700 requests for additional information have been submitted to Westinghouse. Mr. Crutchfield stated that the staff will develop a schedule for the detailed review of the AP600 within the next few months.

The SBWR application needs further information required by the staff before the application can be docketed. The staff expects to complete the SBWR application in the near future. Mr. Crutchfield stated that a delay in the schedule is expected because of insufficient resources.

Mr. Crutchfield asked the ACRS to continue its support in reviewing the advanced reactor designs in parallel with the staff. He anticipates that the staff will have the ABWR review schedule through the Commission in the March 1993 time frame. The staff expects the Commission to provide details, such as the order and sequence of the advanced reactor designs for the remaining schedules, by April /May 1993.

Mr. Michelson asked about a Crutchfield letter to Dr. Shewmon, dated February 9,1993 concerning the new schedule for the ABWR review. Mr.

Crutchfield stated that the letter was put out as a strawman for ACRS consideration as to how best to accelerate the review schedule. Mr.

Michelson stated that the proposed scnedule in the February 9,1993 letter is speculative at this time and the final ACRS review schedule should be based on the promised GE submittal. Mr. Murley interjected by saying that the letter was not meant to inhibit the Committee from taking the time it l feels it needs for its review. '

Conclusion This was a briefing for information only. No ACRS action was taken at this meeting as a result of this briefing.

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394th ACRS Minutes 7 IV. REACTOR OPERATING EXPERIENCE ON RESTART OF THE FITZPATRICK NUCLEAR PLANT (0 pen)

Note: Mr. Boehnert was the Designated Federal Official for this portion-of the meeting.  ;

Introductory Comments

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The ACRS was briefed on the restart of the James A. Fitzpatrick Nuclear i Plant, which is a BWR/4 Mark I plant that generates 820 MW(e).that. began-commercial operation in July, 1975. In November,1991 the licensee, New.  ;

York Power Authority (NYPA) shut the plant down due to the discovery'of a. .

problem with the containment isolation logic in the core spray system. .It '

was found that this defect had existed in the plant since initial startup. i This fact, combined with the NRC's concern over apparent' declining -

performance trends initially categorized in an early-1991 SALP review and -

subsequent NRC Diagnostic Evaluation Team (OET) inspection, spurred the-licensee to conduct additional investigations. These investigations led to the discovery of numerous violations of fire protection requirements. - i The licensee elected to keep the plant shut down until it was confident -

that all major problems were resolved. The ~ NRC did not issue . a r

" Confirmatory Action Letter" in connection with NYPA's shutdown decision.  ;

Licensees Presentation

• i Mr. Beedle, Executive Vice President of Nuclear Generation, noted the following key points: ,

The root causes of the licensee's problems were (1) inadequate

• management oversight, direction and support, (2) ineffective planning and resource allocation, and (3) lack of policies to promote and enforce performance standards.

Two key improvement initiatives are the Results Improvement  ;

Program, designed to provide a plan for continuous improvement, t and a Nuclear Generation Business Plan, whose key objectives include promotion of nuclear and industrial safety, professionalism, ;arformance, regulatory compliance, and cost management. In ;distion, a number of steps were taken to improve the " safety culture" of the organization.  ;

?,provement to the management and organization was accomplished by both an extensive change in management. personnel and the restructuring of the NYPA organizational structure. These changes included: a new plant manager, addition of three new '

general manager positions, new plant departments, and the addition of about 65 new positions. Nuclear leadership and plant  :

leadership teams were created to ensure the permanence of the ,

corrective changes.

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. Extensive physical and capital improvements were made to the plant in order to bring it into full regulatory compliance and to ensure the plant can be a top performer.

In response to questions from Mr. Carroll, Mr. Beedle noted that INP0 had rated the plant as being in trouble. Beedle also noted that the Diagnostic Evaluation Team (DET) did not identify any problems that he had not seen, himself. It was noted that commercial operation of the FitzPatrick plant is viable as long as the plant's capacity factor is >75 percent.

NRC Staff Presentation Mr. Cowgill, NRC Region I Office, noted that he was the Chairman of the NRC's FitzPatrick Restart Assessment Panel. He discussed the details of .

the staff's review of NYPA's Restart Improvement Program, noting that the staff had concurred in NYPA's assessment and that NYPA was ready to restart the plant in late-December 1992. The plant has been restarted and is now running at full power. It was noted that the FitzPatrick Nuclear Plant is on the NRC's " Watch List" and the staff is continuing to closely follow-up on NYPA's implementation of the Restart Improvement Program.

Conclusions Members of the Committee expressed their satisfaction with the corrective actions specified in the Restart Improvement Program and with the NRC staff's review of this matter.

V. NRC REGULATORY REVIEW GROUP (0 pen)

Note: Mr. Houston was the Designated Federal Official for this portion of the meeting.

Mr. J. Sniezek, Deputy EDO and Managing Executive for the Group, introduced this topic noting that the Regulatory Review Group had only been in existence for about a month and that the Charter for the Group had just been approved by the Commission on February 2,1993. He indicated that the task for the Group is to determine what revisions to NRC regulations, guidance and practices, should be made to give increased flexibility to the industry and plant operations without negatively impacting overall reactor safety.

Mr. F. Gillespie, NRR Review Group Leader, made some introductory remarks and indicated that the Group was trying to identify those elements of the  :

regulatory structure of practices that are prescriptive and could possibly be altered. He noted that the principles of good regulation imply that .

the NRC continually upgrade the regulations to provide the utilities with ]

the most efficient options. He further indicated that the presentation would be divided into three sections; (1) regulation review, (2) license analysis and (3) risk assessment.

t 394th ACRS Minutes 9 Mr. J. Jaudon, Region IV, presented a states report on the review of regulations and supporting documentation. He indicated that the initial effort had been directed toward 10 CFR 21,50 and 73. He noted that from their initial screening there were 54 areas where the licensee had the control and management with the NRC only on notification. He discussed problems and discrepancies that were found during the review of the security program emergency plan and the QA program.

Mr. C. Thomas, NRR, discussed some preliminary findings from the assessment of four operating plant licensees (Seabrook, Surry, Perry and Peach Bottom). Each plant license contained about 350 numeric items with about 10 percent of them being assessed in detail. In closing, he indicated that the first pilot review should be finished around February 19, 1993 and that this Subgroup's final report should be issued on or about May 5, 1993.

Dr. J. Murphy, RES, discussed the assessment of the strengths and weaknesses of PRA methods and of the use of PRA to improve plant operations. The PRA Working Group, chaired by Mr. Cunningham in RES, is looking at the use of PRA within the NRC. He discussed the principles for use of integral PRA analyses in regulation and presented an example of risk-based analyses in setting the allowable outage time for some selected systems.

Mr. Gillespie closed this session with some discussion of graded QA plans, security programs and technical specifications. Mr. Lindblad expressed a concern that this effort seemed to be expanding the body of regulations rather than reducing them.

Conclusions This was a briefing for information only. No ACRS action was taken at this meeting as a result of this briefing.

VI. MULTIPLE SYSTEMS RESPONSE PROGRAM (0 pen)

Note: Mr. Coe was the Designated Federal Official for this portion of the meeting.

Introductory Comments Mr. C. Michelson introduced this topic to the Committee by noting that the Multiple System Responsa Program (MSRP) was conducted to bring together and to individually characterize numerous issues and concerns that had been raised predominately by the ACRS over many years. He stated that several Unresolved Safety Issues had been resolved by allowing ancillary l concerns to be captured by the MSRP. Currently the MSRP is complete and the twenty-one issues that were identified have been or are being prioritized by NRC Research (RES). He noted that the degree to which these issues are being addressed by the evolutionary and advanced plant ,

designs varies widely between issues. Finally, the purpose of this '

394th ACRS Minutes 10 briefing was described as an opportunity to discuss the progress toward-resolution for each item with the NRC staff.

NRC Staff Presentation Mr. Emrit, Engineering Issues Branch in the Division of Safety Issues Resolution in the Office of Nuclear Regulatory Research, stated that the twenty-one issues characterized by the MSRP were published in NUREG/CR-5420 and that RES had found seventeen of the issues being addressed as a part of other Generic Issues or programs. Three more of the twenty-one issues were considered by RES as having low enough significance that they should be dropped. the remaining issue was still being evaluated.

Mr. Emrit itemized each issue and described the program into which each of the issues had been incorporated. The three dropped items were as follows:

. Common cause failures related to human errors

. Nonsafety-related control system / safety-related protection system dependencies

. Environmental qualification of seals, gaskets, packing and lubricating fluids associated with mechanical equipment.

The item still being evaluated was:

. Synergistic effects of harsh environmental conditions.

All otner items were described as being incorporated into one of the Generic Issues identified and prioritized in NUREG 0933 "A Prioritization of Generic Safety Issues" or the Individual Plant Examination of External Events (IPEEE) program.

Mr. Baer offered to present a more formal briefing on the status of resolution of each of these items in the summer.

Conclusions The Comittee made no conclusions or determinations during this meeting.

VII. ATOMIC SAFETY AND LICENSING BOARD PANEL (0 pen)

Note: Mr. Houston was the Designated Federal Official for this portion of the meeting.

Introductory Comments Dr. Shewmon indicated that members of the Atomic Safety and Licensing Board panel (ASLBP) had been asked to provide this briefing by describing their current activities to the Committee.

394th ACRS Minutes 11 Conments from Reoresentatives of the Atomic Safety and Licensina Board Judge Paul Cotter, Chief Administrative Judge of the Atomic Safety and Licensing Panel (ASLBP), briefed the Committee on the ASLBP hearing process.

Judge Frederick Shon, Deputy Chief Administration Judge - Technical, discussed the lawyer - technical member relationship that exists on each Board made up of two technical people and one lawyer. He briefly noted a listing of safety improvements that had resulted from the hearing process.

In this list, he noted 12 improvements in the category of generic matters and 12 plant specific matters.

Mr. Lee Dewey, Director and Chief Counsel, discussed the role of ASLBPs in design certification proceedings. He noted OGC's recommendations as given in SECY-92-381 as to the role of Licensing Boards. The following topics were discussed:

a limited magistrate voice, full magistrate role (0GC has recommended a modified full magistrate - No commission approval as yet)

• sua-sponte authority a rulings on hearing requests, matters of controversy and additional hearings

• threshold for intervenor participation

• handling of proprietary information Conclusions This was a briefing only. No Committee action was taken at this meeting as a result of this briefing.

VIII. BRIEFING ON RECENT CHANGES TO THE REGULATIONS ON THE CONDUCT OF GOVERNMENT EMPLOYEES (0 pen)

Note: Mr. Quittschreiber was the Designated Federal Official for this ,

portion of the meeting. l Representatives of the Office of the General Counsel briefed the Committee on the Standards of Ethical Conduct for Employees of the Executive Branch (including Part I of Executive Order 12674 and 5 CFR Part 2635 Regulation) as it relates to Special Government Employees (SGEs). This briefing was  :

different from regular NRC staff briefings since the Committee has a different set of specific needs.

Specific comments made by Mr. Rothschild and Mr. Szabo included the following:

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. NRC employees should always rely on the Ethics Counselor's advice, even if the advice is wrong the agency will not take action against the >

employee. The Ethics Counselors in the NRC include OGC staff members:

Rothschild, Fehst, Parler, Fitzgerald, and Szabo.

. ACRS members, as SGEs, can get paid honorariums and travel expenses for speeches, but not for a specific speech on ACRS activities.

. ACRS members can be paid for teaching outside the NRC but should not use their ACRS affiliation as the basis for teaching.

. If members receive an award of more than $200.00 from a prohibited ,

source (e.g., licensee), they must first get approval of an Ethics Counselor before accepting.

• SGEs cannot work for a foreign country or entity owned by a foreign government (This does not include either the IAEA, since the U.S. is a member, or foreign corporations). It was noted that members may participate on review committees for a foreign government's laboratory with a small amount of pay, but first must get approval from an Ethics '

Counselor.

. No mutual funds are on the list of prohibited stocks at this time.

• Some might be added that deal exclusively with nuclear utility stocks.

0GC takes responsibility for the correct and complete listing of stocks on the list. Any stocks not on the list are acceptable for purchase.

. SGEs can accept meals of less than $20.00 each but not to exceed $50.00 per year from any prohibited source. SGEs can accept gifts from a foreign government of up to $200.00 (Meals etc.) at meetings. However, if non foreign government people are in attendance, an SGE can accept meals up to the per diem amount for the country they are visiting. If the function is widely attended, and with NRC interest and with the ACRS Chairman's approval, members can accept meals etc., the same as others at the function. >

. ACRS wmbers, upon leaving the Committee, can work for others on matten they worked on with the ACRS, but cannot sign and send such matters to the NRC or appear before the NRC on anything specifically worked on during their time with the ACRS.

Conclusions This was a briefing for information only. No ACRS action was taken at this time.

IX. ACRS SUBCOMMITTEE ACTIVITIES (0 pen / Closed)

Note: Dr. Larkins was the Designated Federal Official for this portion of the meeting.

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Report of ACRS Plannina and Procedures Subcommittee Meetina on February >

10. 1993. 1993 (0 pen / Closed)

The minutes of the February 10, 1993 Planning and Procedures Subcommittee meeting were discussed. There was general agreement with the minutes 'of that meeting with the following comments:

Accointment of New Members (Closed)

This portion of the meeting is reported in a special closed meeting -

supplement, which is attached.

Privacy and Use of the ACRS Bulletin Board The Committee agreed to the following with regard to the ACRS staff reading private bulletin board messages:

• The system operators (Sysops) will not read " Receiver Only" (private) messages addressed to persons other than the Sysops, except under special circumstances. (Note: a " DISCLAIMER" has been added to the bulletin board menu explaining those rare circumstances under which private messages might be read and/or copied by the Sysops.)

The users of the bulletin board system should label only those messages

" private" that they really intend to be kept private.

Meetina Dates for the Multilateral Meetina The members confirmed that the proposed dates of October 11-15, 1993 for

• a multilateral meeting of advisory committees to be held in France was acceptable. The French and the Germans should be notified of the acceptability of these dates.

X. FUTURE ACRS ACTIVITIES (0 pen) -

Note: Dr. Savio was the Designated Federal Official for this portion of the meeting.

The following activities were scheduled for the 395th ACRS Meeting, March 11-13, 1993, Bethesda, MD:

Current license Renewal Issues - The NRC staff will brief the Committee on the status of current license renewal issues, including the establishment of a senior management review group to review the  ;

harmonization of the Maintenance and License Renewal Rules. j l

- Computer Issues - The NRC staff will brief the Committee on the need  ;

for and progress toward the staff's development of standards and '

criteria for digital Instrumentation and Control Systems and the staff's policy on diversity (backups).

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. Reactor Ooeratina Experience - The NRC staff will brief the Committee regarding the reactor trip and stuck open pressurizer safety valve ,

event of July 3, 1992 that occurred at the Fort Calhoun Nuclear Power Plant. Representatives of the licensee and of the NRC 1 staff will participate, as appropriate.

. ISO Ouality Standards - The NRC staff will brief the Committee regarding the ISO 9000 quality management standard used by the European community, and how it differs from the quality standards being used.in i the U.S. nuclear industry.  ;

ACRS Subcommittee Activities - Members of the Committee will report on i and discuss the status of ACRS subcommittee assignments, including alternate plugging criteria for degraded steam generator tubes, piping design improvements for advanced plant designs,_and proposed priority ranking of Generic Issue 152, " Design Basis for Valves that Hight be Subjected to Significant Blowdown Loads," PWR version of the RELAP5/M00-3 code and the analytical and experimental programs in support of the AP600 design certification effort, and procedures for the conduct of ACRS business. Representatives of the NRC staff will participate, as appropriate.

Reconciliation of ACRS Comments and Recommendations - The members will discuss replies from the NRC Executive Director for Operations regarding the NRC staff reaction to recent ACRS comments and .

recommendations. ,

Future ACRS Activities - The members will discuss topics proposed for consideration by the full Committee.

Prooosed ACRS Reoorts - The members will discuss proposed ACRS reports ,

on computer related issues, Organizational Factors Research Program, l and on AE0D study of human performance in operating events.

Representatives of the NRC staff and industry will participate, as j

appropriate.  ;

Apoointment of ACRS Members - The members will discuss qualifications 4 of candidates proposed for appointment as ACRS members. Portions of I this session will be closed to discuss information the release of which I would represent a clearly unwarranted invasion of personal privacy.

Miscellaneous - The members will discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of topics that were not completed during previous meetings as time and availability of information permit.

XI. RESEARCH ON ORGANIZATIONAL FACTORS (0 pen)

Note: Mr. Alderman was the Designated Federal Official for this portion of the meeting.

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1 Introductory Comments Mr. J. Carroll introduced the topic by noting that the organizational factors research program has been ongoing since it was revived in 1987 by the NRC Research Staff. The staff has provided a comprehensive review of organizational factors research to the Commission in SECY-93-020 that '

recommends that the development work on measurement tools for organizational performance be concluded. The existing tools are to be considered for use in inspections and diagnostic team inspections. If it.

can be demonstrated that these tools can be used in assessing risk through a PRA, then that effort should be continued. Mr. Carroll indicated that he and other ACRS members believe this research is important and should be continued.

NRC Staff Presentations Mr. J. Kramer, Section Leader in the Human Factors Branch in the Office of Nuclear Regulatory Research, said that organizational factors research has always been exploratory with a need to demonstrate feasibility. The objective of this research has been to identify organizational factors that are important to nuclear plant safety, to' develop techniques that can be used to measure these factors, and to develop products that can be used by the agency to enhance its evaluation of nuclear power plant organizational performance.

The NRC staff conducted a comprehensive review of organizational factors research results, and reported their findings to the Commission in SECY-93-020, Review of Organizational Factors Research, dated February 1,1993.

In that report, the staff concluded that the gathering of organizational factors data is resource intensive. He felt that there is a relative low cost effectiveness in conducting regulatory research in this area beyond 1993, or until such time that it is determined that organizational factors can be reliably integrated into PRA models.

Presentation by Brookhaven National Laboratory Dr. S. B. Haber, Brookhaven National Laboratory (BNL), presented the results of the organizational factors research being performed at BNL. She noted that their research has identified five factors important to safety (culture, communications, decision-making, administrative knowledge, and human resources allocation). The factors were subdivided into 20 subcategories called dimensions. Following identification of the factors and dimensions, the next step was develop a systematic way to look at these organizational factors and dimensions.

Ms. Haber described three techniques used for application of this research: <

1. A structured interview protocol, consisting of interviews using a database by trying to ascertain information on the factors and dimensions.

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2. A behavioral anchored rating scale (BARS). This also uses a interview technique, but in this case specific examples of how factors and dimensions can be applied to a specific plant or organization are discussed. It is possible to quantify how well these factors and dimensions can be applied at a specific plant or organization.

3. A behavioral checklist. Supervisors and managers were observed performing the functions they do to complete assignments. Based on these observations, behavior checklists were developed that can be used by individuals with limited training. The checklist consists of a series of questions that can be answered by yes, no, or not applicable.

In response to Committee questions regarding what is a validated tool, Ms. Haber replied that it is one that really measures what it is supposed to measure.

In response to a question from Mr. Ward on whether there was any empirical evidence that a given score is related to some given level of safety performance, Ms. Haber replied that to be able, to use these tools with any confidence, a lot more validation effort is needed.

Ms. Haber discussed a quantification matrix based on either 20 dimensions or 5 factors. This allows a standardized assessment of organizational factors across the plants by various groups.

Ms. Haber briefly discussed BNL's efforts to integrate research into the PRA process. Dominant accident sequences characterizing 93 percent of core melt frequency were identified. The cutsets within those sequences were determined, and the human errors in them were identified. The human errors were grouped with respect to uncertainty factors. These uncertainty factors were then quantified for a specific plant. Based on the previous steps, the effect of organizational factors on the uncertainty factors was determined.

In response to a question from Mr. Carroll as to whethor organizational factors research tools have been developed to the point where they are useful, Ms. Haber replied that in order to use them with any level of confidence more work has to be done. Mr. Kramer estimated that it would cost about 1.5 million dollars to complete this work.

Influence of Oraanizational Factors in PRAs Dr. George Apostalakis, University of California at Los Angeles (UCLA),  ;

discussed the results of organization factors research being conducted by  :

them in the area of integration of organizational factors into PRAs. The l initial step of their study is to find out how nuclear plants are I operated, i.e., how the nuclear managers function by following procedures called work processes. A work process is a standardized sequence of tasks designed within the operational environment of an organization to achieve a specified goal.

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394th ACRS Minutes 17 Mr. Apostalakis used the work process for corrective maintenance as an example. The sequence of tasks are:

1. Maintenance. order requested

2. Prioritize the request

3. Plan the work

4. Scheduling / Coordination

5. Execution

6. Return to normal line-up

7. Documentation ,

Within these tasks can be a number of sub-tasks. For example, execution might include, self verification, quality control, and post-maintenance testing.

The work process includes how things should work. It can be used as a basis for how things can go wrong. Mr. Apostalakis and his associates at ,

UCLA have developed a work process analysis model called WPAM. He presented an illustration of the use of WPAM, citing an example of loss of

• offsite power. The minimal cutset consisted of these events:

1. The initiator, which is loss of offsite power

2. The subsequent loss of emergency AC power due to miscalibration of under voltage relays

3. Station blackout

4. The probability of non-recovery of offsite power during this period of loss of battery power and subsequent onset of core melt is 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Data from the FitzPatrick Individual Plant Examination and information from the Swain Gutman handbook were used to make these calculations.

Using the assumptions and data as described above, a value for the core-melt frequency was presented. Dr. Apostalakis noted that if organizational factors considerations are applied to the calibration  ;

probabilities and quality of maintenance is considered for the station  ;

batteries, then significant changes are observed in the probability of non-recovery of offsite power and core-melt frequency. He pointed that this technique is new and additional work is necessary to verify the results.

Dr. Apostalakis discussed a sensitivity analysis for organizational ,

factors. The first step was to develop an organizational factors matrix that evaluates the factors that affect specific work function tasks. Those organizational factors that have a high correlation with work process tasks are incorporated into an existing PRA. The parameters of the PRA are then compared both with and without the organizational factors input, to determine the sensitivity of the input.

Conclusions l l

This was a briefing for information. No Committee action was taken at this meeting as a result of this briefing. The Committee did consider

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l 394th ACRS Minutes 18 l 1

writing a report on this matter, but the report was rescheduled for the March 1993 ACRS meeting.

XII. RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS (0 pen)

Note: Mr. Duraiswamy was the Designated Federal Official for this portion of the meeting.

Due to lack of time this matter was not discussed at this meeting. It will be scheduled for discussion at the March 1993 ACRS meeting.

XIII. MISCELLANEOUS (0 pen)

Note: Dr. Larkins was the Designated Federal Official for this portion of the meeting.

proposed Rule - Exemption from Criticality Monitorina for Unirradiated Fuel at Liaht Water Reacton The Committee directed Mr. John Larkins to send a memorandum to Warren Minners, Division of Safety Issues Resolution in the Office of Nuclear Regulatory Research, as noted above, indicating that the Committee decided not to review the proposed rule.

ACNW Review of Interim On-Site Storaae of low-level Waste The Committee had no objection to the ACNW reviewing the option for interim on-site storage of low level wastes at nuclear power plants, stemming from an EPRI report on this matter dated September 1992.

The ACNW request to review this matter was discussed in a memorandum to R.

Savio from Mr. G. Gnugnoli, dated February 9,1993. ,

XIV.

SUMMARY

/ LIST OF FOLLOW-UP MATTERS

,a The Committee agreed that October 11-15, 1993 would be an acceptable date for the Multilateral Meeting of Advisory Committees in France.

The ACRS staff should notify the GRS/RSK of the acceptability of this date so that planning for the meeting can continue. (Mr.

Quittschreiber has the follow-up on this matter.)

The ACRS Chairman and the ACRS staff should set up a training program for Russian specialists attending a one day session at the ACRS office on June 3,1993 on the functions of the ACRS. (Mr. Quittschreiber has the followup on this matter.)

=

Dr. Seale asked the representatives of the Department of Energy to provide a copy of the comparison between the advanced reactor policy statements in SECY-88-203, dated July 15, 1988 and the draft policy statements, dated December 16, 1992.

Note: Mr. C. L. Reid, 00E, provided a copy of this comparison on February 18, 1993.

394th ACRS Minutes 19 EXECUTIVE SESSION (0 pen)

XV.

Note: Dr. Larkins was the Designated Federal Official for this portion of.

the meeting.

During its 394th meeting, February 11-13, 1993, the Advisory Committee on-Reactor Safeguards (ACRS) discussed several matters and_ completed the following reports'and memorandum as noted.

Reports

. Issues Pertainina to the Advanced Reactor (PRISM. MHTGR. and PIUS) and CANDU 3 Desians and their Relationshio to Current Reaulatory-Reauirements, (Report to the Honorable Ivan Selin, NRC Chairman, from Paul Shewmon, ACRS Chairman, dated February 19,1993)

. Procosed Resolution of GI-142 "Leakaae Throuah Electrical Isolators in  ;

Instrumentation Circuits." (Report to Mr. James M. Taylor, Executive -

Director for Operations, from Paul Shewmon, ACRS. Chairman, dated February 19,1993)

Memorandum ,

• Proposed Rule - Exemption from Criticality Monitorina for Unirradiated  ;

Fuel at Liaht Water Reactors, (Memorandum to Warren Minners, Director of the Division of Safety Issue Resolution in the Office of Nuclear Regulatory Research, from John Larkins, Acting Executive Director of the ACRS, dated February 19,1993.)

The meeting was adjourned at 11:45 am on February 13, 1993 .

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l l APPENDICES MINUTES OF THE 394TH ACRS MEETING FEBRUARY 11-13, 1993 I. Attendees II. Future Agenda III. Future Subcommittee Activities IV. List of Documents Provided to the Committee l

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APPENDIX I MINUTES OF THE 394TH ACRS MEETING i FEBRUARY 11-13, 1993 ATTENDEES  ;

f FEBRUARY 11. 1991 Puulic Attendees NRC Attendees Fred Silady, GA Pat Madden, NRR  ;

Pete Karcz,. DOE J. Souder, ADM  :

Greg Brown, Tokyo Electric Power Co. L. Soffer, OCM Dan Mears, GCRA J. Jaudon, RIV Vince San Angelo, Bechtel Power T. Corne, RI Jerry Griffith, DOE C. Thomas, NRR Mark Beaumont, Westinghouse G. Wright, EDO J. N. Sorensen, Grove Engineering C. Craig, RVI R. E. Beedle, NYPA T. Tjader, NRR Joseph Zerbo, General Physics M. Drouin, RES J. A. Gray, Jr. NYPA J. Murphy, RES R. Comerse, NYPA B. Siegel, EDO Barry Salmon, NYPA J. Sniezek, EDO Michael Colomb, NYPA J. Cutchin, OGC Ed Borella, EBASCO l T. Dunning, NRR '

Stephen D. Floyd, NUMARC J. OBrien, NRR Phyllis Rich, NUMARC B. Person, NRR David Wade, Argonne National Lab. Crutchfield,NRR Dick Hardy, GE T. Ulses, i Patrick Magee, GE R. Meyer, RES ,

Chong Lewe, NUS D. Scaletti,NRR Robert Ferguson, AECLT J. Donoghue,NRR David Moses, Oak Ridge National Lab. T. Cox, NRR Peter Williams, DOE /NE J. Kennedy, NRR Jeff Herring, PDCO S. Sands, NRR C. L. Reid, PDCO H. Pastis, NRR Nicholas Grossman, DOE C. Abbott, OC Ray Mills, PDCO J. Donohew, NRR J. Tong, AECB Scarborough,0CM 1' A. M. M. Aby, AECB J. Guttmann,0CM David Dilling, Bechtel Group, Inc. D. Carlson, RES l Louis N. R., AECLT E. Thron, NRR A. D. Hink, AECLT T. Kenyon, NRR D. Pendergast, AECLT Borchardt, NRR D. Wright, AECL H. Newsome, OGC l J. Herczel, DOE J. Wilson, NRR  !

Marty Cooper, Westinghouse M. Taylor, EDO l A. J. Neylan, GA R. Capra, NRR

i 4

Minutes of 394th ACRS Meeting, Appendix I FEBRUARY 12, 1993 Public Attendees NRC Attendees Chong Lewe, NUS Paul Norian, RES K. Corens, NUMARC J. Chen, RES Judith Sikorski, Serch Licensing L.Beltracchi,RES G. Apostalakis, UCLA L.Beltracchi,RE Sonja Haber, Brookhaven National Lab. R. Enrit, RES David Cleaves, Mitre W. Lefave, NRR Bob Whitesel, NUMARC H. Pastis, NRR Bob Evans, NUMARC M. Taylor, EDO Tom Leamon, Liberty Mutual Rothschild,0GC J. Szabo, OGC C. Johnson, RES F. Coffman, RES-J. Kramer, RES P. Lewis, RES G. Zech, NRR T. King, RES' M.Fleishman,0CM W. Swenson, NRR W. Beckner, NRR

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APPENDIX II MINUTES OF THE 394TH.ACRS MEETING FEBRUARY 11-13, 1993 FUTURE AGENDA 395th ACRS Meeting, March 11-13, 1993, 7920 Norfolk Avenue, Rethesda, MD, Room P-110. Agenda items are tentatively scheduled.

A. Reactor Operating Exoerience - Briefing and discussion regarding the reactor trip and stuck open pressurizer safety valve event of July 3, 1992 that occurred at the Fort Calhoun Nuclear Power Plant. Representatives of the licensee and of the NRC staff will participate, as +

appropriate.

B. ACRS Subcommittee Activities - Reports on and discussion of  ;

the status of ACRS subcommittee assignments, including.

alternate plugging criteria for degraded steam generator tubes, piping design improvements for advanced plant designs, and proposed priority ranking of Generic Issue 152, ,

" Design Basis for Valves that Might be. Subjected to Significant Blowdown Loads," PWR version of the RELAPS/ MOD-3 code and.the analytical and experimental programs in support of the AP600 design certification effort, and procedures for the conduct of ACRS business. Representatives of the NRC staff will participate, as appropriate.

C. Current License Renewal Issues - Briefing by and discussion ,

with representatives of the NRC staff on the status of current license renewal issues, including the establishment of a senior management review group to review the harmonization of the Maintenance and License Renewal Rules.

D. Future ACRS Activities - Discuss topics proposed for consideration by the full Committee.

E. Resolution of ACRS Recommendations - Discuss replies from r the NRC Executive Director for Operations regarding the NRC staff reaction to recent ACRS comments and recommendations.  ;

r. ISO Ouality Standards - Driefing by and discussion with representatives of the NRC staff regarding the ISO 9000 quality management standard used by the European community, and how it differs from the quality standards being used in the U.S. nuclear industry.

G. Proposed ACRS Reports - Discuss proposed ACRS reports on computer related issues, Organizational Factors Research Program, and on AEOD study of human performance in operating events. Representatives of the NRC staff and industry will participate, as appropriate.

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394th ACRS Meeting Minutes A-II-2:

J H. Computer Issues - Briefing by and discussion with representatives of the NRC staff regarding the need for and progre,s toward the staff's development of standards and criteria for digital Instrumentation and Control Systems and the stsff's policy on diversity (backups).

• I. Anoointmaut of ACRS Members - Discuss qualifications of candidates proposed for appointment as ACRS members.

Portions of this session will be closed to discuss information the release of which would represent.a clearly unwarranted invasion of personal privacy.

J. Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of topics that were not completed during previous meetings as time and availability of information permit.

• Closed ,

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APPENDIX III MINUTES OF THE 394TH ACHS MEETING FEBRUARY 11-13, 1993 i FUTURE SUBCOMMITTEE ACTIVITIES '

Thermal Hydraulic Phenomena,_ March 4 and 5, 1993, Westbank Inn, 475 River Parkway, Idaho Falls, ID (Boehnert), 8:30 a.m.,

Targhec/Bonneville Room.

The Subcommittee will review the status of the PWR version of the RELAPS/ MOD-3 code with emphasis on analytical and experimental programs in support of the AP600 design certification effort. Attendance by the following is anticipated, and reservations have been made at the Westbank Inn ,

(208/523-8000) for the nights of March 3, 4 and 5:

Catton Dhir I Davis Schrock Kress Ward Seale Wulff s

Wilkins Zuber '

Joint Materials and Metallurav/ Structural Encineering, March 10, 1993, 7920 Norfolk Avenue, Bethesda. MD (Igne), 8:30 a.m., Room P-110. The Subcommittees will discuss: (1) the status of the NRC staff's concerns regarding steam generator tube degradation, and (2) the industry proposal on piping design improvements for ALWR plants to reflect current technical knowledge. Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of March 9:

Shewmon NONE Lewis Carroll RESIDENCE INN HOLIDAY INN Lindblad HYATT Catton HYATT Michelson HYATT Davis NONE Seale RESIDENCE INN Kress HYATT Moulder NONE Stevenson NONE Plannino and Procedures, March 10, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 3:00 p.m. - 5:30 p.m., Roon P-422. The Subcommittee will discuss proposed ACRS activities and related  :

matters. Qualifications of candidates nominated for appointment to the ACRS will also be discussed. Portions of this meeting will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.

Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of March 9:

Shewmon NONE Carroll HOLIDAY INN Wilkins HOLIDAY INN

2 H. Computer Issues - Briefing by and discussion with representatives of the NRC staff regarding the need for and progcess toward the staff's development of standards and criteria for digital Instrumentation and Control Systems and  ;

the staff's policy on diversity (backups). ,

• I. Anoointment of ACRS Members - Discuss qualifications-of candidates proposed for appointment as ACRS members.

Portions of this session will be closed to discuss information the release of which would represent a clearly unwarranted invasion of personal privacy.

J.

Miscellaneous - Discuss miscellaneous matters related to the conduct of Committee activities and complete discussion of i topics that were not completed during previous meetings as time and availability of information permit.

Joint Severe Accidents /Probabilistic Risk Assessment, March 18, 1993, 7920 Norfolk Avenue, Bethesda. MD (Houston), 8:30 a.m..

Room P-110. The Subcommittees will begin the discussion of severe accident and PRA issues in regard to the Advanced Boiling Water Reactor (ABWR) Certification Review (Chapter 19 of the ABWR Standard Safety Analysis Report submittal). Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of March 17:

Kress HYATT Michelson HYATT Lewis HYATT Seale HYATT l

Catton HYATT Wylie HYATT Davis NONE Kerr HYATT Lindblad HYATT Ward HYATT Recional Procrams, March 23, 1993, Region II Office, 101 Marietta k Street, NW, Suite 2900, Atlanta. GA (Boehnert), 8:30 a.m. The Subcommittee will discuss the activities of the NRC Region II office. Attendance by the following is anticipated, and '

reservations have been made at the OMNI Hotel (404/659-0000),

100 CNN Center, Atlanta, GA for the nights of March 22 and 23:  ;

Shewmon Michelson Carroll Wilkins NONE I Kress Wylie l l

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• Closed l

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3%th ACRS ttetirg Minutes 3 i

l Joint Meetina of the ACNW Workina Groun/ACRS Subcommittee on Occupational and Environmental Protection Systems, March 26, 1993, 7920 Norfolk Avenue, Dethesda. MD (Gnugnoli/Igne), 8:30  ;

a.m., Room P-110. _The Working Group / Subcommittee _will review the following proposed final regulatory guides related to the implementation of the revised 10 CFR Part 20: (1) DG-8006,

" Control of Access to High and Very High Radiation Areas in '

Nuclear Power Plants," (2) DG-8009, " Interpretation of Bioassay Measurements," and (3) DG-8013, "ALARA Radiation Protection '

Program for Effluents from Materials Facilities," Attendance by the following is anticipated, and reservations have been made at the hotels as indicated for the night of March 25:

Moeller HOLIDAY INN Shapiro NONE Wilkins HOLIDAY INN Kathren NONE Carter NONE '

Advanced Pressurized Water Reactors, April 13, 1993, Windsor.~  ;

Connecticut (Igne). The Subcommittee members will visit the ABB-CE facility at Windsor, Connecticut to observe the System 80+

control room mock-up. Lodging will be announced later. Atten-dance by the following is anticipated:

Carroll Michelson -

Catton Seale Davis Shewmon '

Kress (tent) Wylie '

Plannina and Procedures, April 14, 1993, 7920 Norfolk Avenue, Bethesda, MD (Larkins), 3:00 p.m. - 5:30 p.m., Room P-422. The Subcommittee will discuss proposed ACRS activities and related matters. Qualifications of candidates nominated for appointment ,

to the ACRS will also be discussed. Portions of this meeting will be closed to discuss information the release of which would .

represent a clearly unwarranted invasion of personal privacy.

Attendance by the following is anticipated, and reservations have t

been made at the hotels as indicated for the night of April 13:  ;

Shewmon NONE Carroll HOLIDAY INN Wilkins HOLIDAY INN ,

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3%th ACRS Ftetirg Minutes 4 i

396th ACRS Meetina, April 14-17, 1993, 7920 Norfolk Avenue, Bethesda, MD, Room P-110. Agenda to be announced.

[ NOTE: The April 1993 ACRS meeting will begin on Wednesday, April 14, 1993 to meet with representatives of the NRC staff and industry groups to discuss the NRC staff's' proposals to enhance the Systematic Assessment of Licensee Performance (SALP) pro- '

gram.]

Probabilistic Risk Assessment (tentative) Date to be determined

'(March / April), Bethesda, MD (Houston). The Subcommittee will discuss a proposed regulatory guide on the use of PRA in design i certification and other applications of PRA in the regulatory process. Attendance by the following is anticipated:

Lewis Wilkins Davis Consultants - TBD Kress Michelson Safety Philosophy. Technoloav and Criteria (tentative), Date to be determined (March / April), Bethesda, MD (Houston). The Subcom-mittee will discuss a proposed plan for comparing safety goals with regulations. Attendance by the following is anticipated:

Kress Wylie Davis Kerr Lewis Ward Michelson Thermal Hydraulic Phenomena, Date to be determined (April /May, 2-day meeting), San Jose. CA (Boehnert). The Subcommittee will continue its review of both the GE analytical program (TRACG code) and the experimental programs supporting the certification effort for the Simplified Boiling Water Reactor design. Atten-dance by the following is anticipated:

Catton Dhir Davis Kerr Kress Ward Seale Wulff Wilkins Zuber

394th ACRS Freting Mmutes 5 Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (April /May), Bethesda, MD (Houston). The Subcom-mittees will begin their review of the staff's proposed technical positions on severe accident issues for future plant designs.

The topics of fuel-coolant interactions and hydrogen will be discussed. Attendance by the following is anticipated:

Kress Shewmon Catton Ward Davis Kerr Lindblad Lee Michelson Dhir Seale Thermal Hydraulic Phenomena, Date to be determined (2-day meet-ing), (May), Orecon State Universitya CorvAl_lis, OR (Boehnert).

The Subcommittee will continue its review of the Westinghouse and NRC integral systems and separate effects test programs support-ing the AP600 design certification effort. Attendance by the following is anticipated:

Catton Dhir Davis Kerr Kress Schrock Seale Ward Wilkins Wulff Zuber Decay Heat Removal Syst<1ng, Date to be determined, Bethesda, MD (Boehnert). The Subcor cee will continue its review of the NRC staff's proposed final resolution of Generic Safety Issue 23,

" Reactor Coolant Pump Seal Failures." Attendance by the follow-ing is anticipated:

Catton Michelson .

Davis Wylie Lindblad Ward Thermal Hydraulic Phenomena, Date to be determined, Bethesda, MR I (Boehnert). The Subcommittee will continue its review of the NRC staff program to address the issue of interfacing systems LOCAs.

Attendance by the following is anticipated:

Catton ,

Dhir Davis Kerr Kress Schrock Seale Ward Wilkins Wulff Zuber

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394th ACRS Ebeting Minutes 6  !

Joint Thermal Hydraulic Phenomena / Core Performance, Date to be determined, Bethesda, MD (Boehnert). The Subcommittees will continue their review of the issues pertaining to BWR core power '

stability. Attendance by the following is anticipated:

Catton Dhir Wilkins Kerr Davis Lee Kress Lipinski Seale Zuber Shewmon Joint Severe Accidents / Thermal Hydraulic Phenomena, Date to be determined (Fall), Bethesda, MD (Houston). The Subcommittees will continue the discussion of the technical positions on severe accident issues for future plant designs. The topics of basemat penetration and direct containment heating will be discussed.

Attendance by the following is anticipated:

Kress Shewmon Catton Ward s Davis Kerr Lindblad Lee Michelson Dhir Seale I

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APPENDIX IV MINUTES OF THE 394TH ACRS MEETING FEBRUARY 11-13, 1993 LIST OF DOCUMENTS RECEIVED BY THE COMMITTEE INote: Some of the materials listed may have been provided for ACRS Internal Committee Use Only or may contain Proprietary Information1 ACRS MEETING HANDOUTS AGEMLA DOCUMENTS ITEM N0.

12.2 ACRS Review of AE00 Special Study: " Human Performance in Operatina Events"

1. Memorandum for ACRS Members from P. Boehnert, dated February 10, 1993, re: ACRS Review of AE0D Special Study: " Human Performance in Operating Events", [with enclosures) 13.1 Future ACRS Activities - 395th ACRS Meetina March 11-13. 1993

2. Memorandum for ACRS Members from R. Savio, dated February 12, 1993, re: Future ACRS Activities

3. Memorandum for R. Fraley from James Blaha, dated February 5,1993, re: Proposed Agenda Items for the ACRS/ACNW

4. Letter for James Taylor from David Ward, dated May 14, 1992, re: .

Advance Notice of Proposed Rulemaking on Severe Accident Plant Performance Criteria for Future LWRS

5. Letter for W. Cavanaugh from S. Ebneter, dated December 18, 1992, re: Confirmatory Action Letter

6. Memorandum for Warren Minners from Eric Beckjord, dated January 22, 1993, re: Generic Issue 152, " Design Basis for Valves that Hight be Subjected to Significant Blowdown Loads"

7. Memorandum for Raymond Fraley from Warren Minners, dated January 13, 1993, re: Proposed Rule - Exemption from Criticality Monitoring for Unirradiated Fuel at LWRS [with enclosures]

8. Letter for The Honorable Bob Graham from Dennis Rathbun, re:

Proposed 10CFR Part 70

9. Letter for The Honorable Peter Kostmayer from Dennis Rathbun, re: 10 CFR Part 70

10. Letter for The Honorable Philip Sharp from Dennis Rathbun, re: 10 CFR Part 70 15 Summary Minutes of Plannina and Procedures Subcommittee Meetina -

February 10. 1993

11. Summary of Minutes ACRS Planning & Procedures Subcommittee Meeting February 10, 1993 [ Internal ACRS Use Only]

MEETING HANDOUTS OTHER THAN ACRS

12. DOE Letter for Stephen Sands from Nicholas Grossman, dated January 25, 1993, re: Commission Papers on Policy Issues and Schedules Concerning the Preapplication Reviews of Advanced Reactor and CANDU 3 Designs

13. DOE Letter for Jack Donohew from Peter Williams, dated January 25, 1993, re: Issues Pertaining to the Advanced Reactor (PRISM, MHTGR, and PIUS) and Current Regulatory Requirements [with enclosure]

A 394th ACRS Meeting Minutes, Appendix IV 2

14. MHTGR Designs Response to NRC Key Issues, by Fred Silady, GA, dated February 11, 1993 [ slides]

15. Some Thoughts on Using Safety Goals, by T. Murley [ slides]

16. Letter for Dennis Crutchfield from David Hoffman,' dated January 28, 1993, re: Commission Papers on Policy Issues Concerning the ,

Preapplication Reviews of Advanced Reactors [with attachment] '

17. Presentation to ACRS, Advanced Liquid Metal Cooled Reactor Modular High Temperature Gas-Cooled Reactor, by Jerry'Griffith, DOE, dated February 11, 1993

18. Item #2 Advanced Liquid Metal Reactor (PRISM), dated February 11, 1993 [ slide]

19. Letter for Paul Shewmon from James Taylor, dated February 11, 1993, re: Proposed Resolution of Generic Safety Issue 120 "On-Line Testability of Protection Systems" [with enclosure]

20. Note for R. Savio from G. Gnugnoli, dated February 9, 1993, re: Dr.

Hoeller's Interest in Interim On-Site Storage of low-level Waste

21. 1993 Ethics Training, Ethics Counselors*

J. Szabo, L. Michael Rafky, Geraldine Fehst [ slides]

22. Presentation to ACRS, The ASLBP's Role in Design Rulemaking Proceedings, February 12, 1993

23. Hearings and Safety Improvements: John Shon

24. Memorandum for ACRS from B. Paul cotter, dated February 12, 1993, re: ASLBP Briefing on the Hearing Process

25. James A. Fitzpatrick Nuclear Power Plant, by Ralph Beedle, NYPA  ;

[ slides] ,

26. Letter for Forrest Remick from James Taylor, dated October 18, 1989, re: Proposed Resolution of Generic Issue-128 Electrical Power Reliability

27. Assessment of Regulations Affecting Power Reactors, by Regulatory Review Group / Subgroup [ slides)

28. NRC Staff Presentation to the ACRS, re: Fitzpatrick Restart, by C.

J. Cowgill [ slides] ,

29. Excerpt from The Energy Daily, dated February 10, 1993, NRC Watch List Shrinks, Commission Lauds Com Ed .

30. Excerpt from The Energy Daily re: Scaling Back, Highlights from '

President Clinton's order to cut government jobs and perks, require each agency to eliminate at least on-third of Advisory Committees .

and Commissions not mandated by Congress by the end of the year l

31. Reports / Letters Scheduled for Consideration During the February 11- !

13, 1993 ACRS Meeting

32. Letter for Paul Shewmon from Dennis Crutchfield, February 9,1993,  :

re: Review Schedule for the Advanced Boiling Water Reactor (ABWR)

33. Schedules of NRC Review of Proposed Advanced Light Water Reactor Designs, by Dennis Crutchfield, February 11, 1993 MEETING NOTEBOOK TAB NO.

2 Key Policy Issues for Advanced Reactor Desians

34. Tentative Schedule

35. Status Report

36. Draft SECY-paper: Issues pertaining to the Advanced Reactor PRISM,

, . . . . _ _ . . _ _ . _ .~ - .. . _. _ _.

-[

l 394th ACRS Meeting Minutes,_ Appendix IV- 3 .

y MHTGR, PIUS and CANDU 3 ' Designs and their Relation to Current'  !

Regulatory Requirements  :

37. SECY-92-393, " Updated Plans and Schedules for the Preapplication' i Reviews of the Advanced Reactor, dated November 23,-1992 "

38. Letter for David Nulton from John Larkins, dated January 19,'1993,;

re: Invitation to the Department of Energy staff to attend _394th

~

ACRS Heeting on February 11-13, 1993

39. Letter for Dennis Crutchfield from A. D. Hink, dated January 25, ~

1993, re: -Commission Papers on Policy Issues and Schedules-. 1 Concerning the Preapplication Reviews of Advanced Reactors and CANDU  !

3 Designs . . .

40. Memorandum for J. Ernest Wilkins from Dave Ward, dated January 15,. i 1993, re: Comments on subcommittee meeting of January 6, 1993-3 41.

-Schedules for the NRC Review of Proposed Reactor Desians Status Report j

42. SECY-91-161, Schedules for the Advanced Reactor Reviews 'and ,

Regulatory Guidance Revisions,. dated May 31, 1991

43. ACRS Letter, to Chairman Selin from David Ward, dated July 18, 1991, t re: Schedules for Advanced Reactor Reviews '

44. ACRS Letter, to Chairman Selin from David Ward, dated August 13, 1991, re: Additional Comment on Schedules for Advanced Reactor Reviews

45. SECY-92-393, Updated Plans and Schedules for- the Preapplication Reviews of the Advanced Reactor (MHTGR, PRISM, and PIUS) and CANDU3 1

Designs, dated November 23, 1992  ;

Reactor Operatina Exoerienqa 4

46. Schedule 1

47. Project Status Report I

48. Letter to Ralph Beedle'NYPA, from Thomas Martin, dated December 29, i 1992, re: Restart of the Fitzpatrick Power Plant .

l

49. Letter to Thomas Martin from Ralph Beedle NYPA, dated December 17, 1992, re: Readiness to Restart i

50. Chart of management-level organization for the Fitzpatrick plant.  !

51. NYPA document: Results Improvement Program  :

52. Notification of Significant Enforcement Action, EA 92-033 dated ,

January 29,.1993, re: Imposition of Civil Penalties, l 5 NRC Reaulatory Review Grouc l

53. Tentative Agenda j

54. Status Report  ;

55. Memorandum for the Commissioners from James Taylor, dated January _4, -l 1993, re: COMIS-92-025 Regulatory Review

56. Memorandum for H. Lewis from Dean Houston, dated January 26, 1993, re: Commission Meeting with NUMARC on Industry - Review of - NRC Regulations and Regulatory Processes, January 21, 1993

57. Memorandum for James Taylor from Samuel Chilk, dated December '24, 1992, re: COMIS-92-025 Regulatory Review 8 Multiple System Response Proaram

58. Proposed Schedule

59. Project Status Report

60. Draft Report Evaluation of Potential Safety Issues Resulting from the Multiple System Responses Program (NUREG/CR-5420)

61. ACRS Letter Reports regarding MSRP and related subjects:

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394th ACRS Meeting Minutes, Appendix IV 4

= Resolution of USI A-46, " Seismic Qualification of Equipment in Operating Plants", dated September 17, 1986 i

. Proposed Resolution of US! A-17, " Systems Interactions in Nuclear Power Plants dated May 13, 1986

• Proposed Resolution of USI A-47, " Safety Implications of Control Systems", dated April 12, 1988

62.

• Proposed Resolution of USI A-17, " Systems Interactions in Nuclear Power Plants", dated August 16, 1988

63. Proposed Resalution of USI A-47, "Safecy implications of Control Systems", datea August 16, 1988

64.

• Resolution of GI-43, " Air Systems Reliability," dated January 19, 1989 >

65. = USI A-17, " Systems Interactions in Nuclear Power Plants" dated June 13, 1989

66.

• Proposed Resolution of Generic Issue 128, " Electrical Power Reliability" dated June 14, 1989 9 atomic Safety and Licensina Board Panel Activities

67. Tentative Agenda

68. Status Report

69. ASLBP Section from the 1991 NRC Annual Report

70. ASLBP Organization Chart of January 31, 1992 Membership Listing of the ASLBP

~

71.

12 Research on Oraanizational Factors

72. Presentation Schedule

73. Project Status Report Attachments to Project Status Report:

• Proposed SECY Paper "Sent to SECY on 2/1/93," Review of Organizational Factors Research a Excerpt from proposed Minutes of November 1992 ACRS Meeting -

Discussion on AEOD Analysis of Human Factors Aspects of Operating Events [ Internal Use Only]

. Memorandum for J. Carroll from Dave Ward, dated November 16, 1992, re: Comments on 11/12/92 Senior Management Meeting " Products and Applications Resulting from Organizational Factors Research"

. Letter to Paul Boehnert from Tom Leamon, dated December 2,1992, re: Organizational Factors Research (Proprietary Info)

. Memorandum for J. Carroll from P. Boehnert, dated December 3, 1992, re: NRC Senior Management Meeting: Product and Applications Resulting from Organizational Factors Research - Meeting Summary and Consultant Reports [ Prepared for Internal Committee Use]

= NUREG-1275 Volume 8: " Operating Experience Feedback Report - Human Performance in Operating Events."

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