ML17202V021

Summary of ACRS 368th Meeting on 901206-08 in Bethesda,Md Re Full Term OL Conversion for Plants

ML17202V021
Person / Time
Site:	Dresden, Palisades
Issue date:	12/06/1990
From:	Advisory Committee on Reactor Safeguards
To:	Advisory Committee on Reactor Safeguards
References
ACRS-2734, NUDOCS 9103180336
Download: ML17202V021 (50)

Text

r. "".

i TABLE OF CONTENTS MINUTES OF THE 368TH ACRS MEETING DECEMBER 6-8, 1990 Page No.

I.

Chairman's. Report.... *'*.~.......... ~............. -...............

1 II.

Full Term Operating License (FTOL) Conversion for the *Dresden N.uclear Power Station,. Unit *.** * **.*.. ; *.*.....*.*.*... *.... *...

1 III.

FTOL Conversion *for the Palisades Nuclear Plant..............

6 IV.

High-Level Radioact;:i ve Waste Disposal. *** ;.**** *.... * * * * *......

7

v.

Certification ~f.. Standardized Plant Designs *.** ~~************** 10 VI.

Nuclear Power Plant Operating Experience and Events *********.. 14 VII. *Development of New standardized Technical Specifications *.... 18 VIII.

NRC Safety ~esearch Program.....*... ~*********************** 21

• lX'.. *~xecutiv~ Session$.~................ ;._......... ~................... -*23, A. Reports to the commission *.****. * : ********.*...*** * **** *.* ~ *. ~

• 2 3 SECY-90-377, ** "Requirements for Design Certification* Under...

10 CFR Part 52" (Report to Chairman.Carr dated.December 10,

~990) ** ~ ******** -... **~:*** *** * -** *-* * ********* *.*.; ********* ~. *-.~.* **...

• 23 Full-Term Operating License for the Dresden Nuclear Power Station,* Unit 2 (Report to Chairman.Carr dated Decemberll,..

~ -19 9 0 ) * * * * * * * * ~ * * *.. * * * * *. * * * *.. * * *. * *. * *. * * * *.. * *. *. * *........ 2 3

• Full-Term Operating License for the Palisades Nuclear Plant (Report to Chairman Carr dated.December i'1, 1990) ** ~.......

2*4

.. Westinghouse's Application for Preliminary Design Approval for the RESAR SP/90 Des~gn (Report to Chairman Carr dated December 12, 1990)._ ** _ ** -.-**.*.*.***.*..*.** *....*. *. -.*... _ **. _... *.

24 B. Memoranda * ** ; *******..**.*****.*.***** *......................

~ *-~.,. 2 5 Press Announcement -

ACRS Vacancy (Memorandum for John Kopeck, Office of Governmental and Public Affairs~* from Mabel F. Lee, ACRs,* dated December 11, 1990) ***.*...** *****.

25 Prescheduled ACRS.Meetings with the Commissioners (Memo-randum for Samuel J.* Chilk, Secretary of the Commission;.

from R.

F~ Fraley, ACRS, dated December 14, 1990)..*...... ~.*.25 C. Subcommittee Report... :.. *... *.. *...... *...... I!'* *****

-.* ****** ~ *

• 2 5 Adopted Plants Aqtivity....**.......... ~.................. ~

25 D~ Othe~ Matters......... ~.............. *'*.... :.. *..............

26 Election of ACRS Offi6ers for CY 1991... ~********~**\\....*.

26 E. Summary /List of Follow-Up Matters.......................... ;

2 6 F. Futur.e Activities (open)........................*..........

--- 1.- -*- *Fµture Ag,enda. _........ _. _....................................

r 1

2.

Future Sub. co~1 ttee ~ct1 vi ties.........................

9103~80336 9012()6

\\

~. ~~,0 ~DOCK O~OO~fi~7 ii..

'\\<S~\\\\.

29 29 29

,.. I.

Attendees II.

Future ~genda A\\*

ii APPENDICES 368TH ACRS MEETIN~

• DECEMBER 6-8 I 1990 III.. Future Subcommittee Activities IV.

List of Documents Provided to the Committee

. I

/,

i Federal Register I Vol. 55, No. 228 I Tuesday. November 27, 1990 /

30J~

. f)';f<}' / i;fr,-8 /9 Notices 49353

3. Roy Williams of MISER indicated that MISER iS correnUy extending the~ populatoo p<ojections into the 21st century..

4. The entire towns of Plymouth. Kingston and Duxbury lie within the.Polgrom EPZ. It IS estimated that 58 percent of the population in Carver. and 6 percent of the

_Marshfield population re;;ide within the EPZ. The above figures are those within the EPZ.

[FR Doc. 00-2noo Filed 11~26-90; 8:45 am) 61LLING*COOE 759CHl1-M

. be permitted only during those portions conv,ersions of provisional operating_

• .of the meeting.when a transcript is being. licenses to full term operating licenses kept. and questions may be asked only for the Palisades Nuclear Plant and the

. by members of the Committee, its Dresden Nuclear Power Station. Unit 2.

Advisory Committee *on Nuclear..

consultants, and staff. The office of the.

Representatives of the l:'JRC staff and Waste; Meeting ACRS is providing staff support fqr the the licensees-will participate, as '

The Advisory Committee on Nuclear

ACNW. ~ersons desiring to make oral appropriate.

Waste (ACNW) will hold its 26th statements should notify the Executive

. Portions of this session will be closed-Director of the office of the ACRS a*s far

• as necessary* to d1'scus.s Propn'etary mee1ing on December 12-14, 1990, room

...z lk th in advance as practical so that Intorma.t1'on applicable 'to the operation P-110, 7920 Nono Avenue, Be esda, b

d

. MD, 8:30 a.m. until 5 p.m. each day. The. appropriate, arrangements can e ma e of these plants. -.

t.

will b t th bl' - - tq allow the* n~eessary time during the.

. 1:30 p.m."-3:30 p.m.: certification of

• en ire meeting

e. 9pen ° e pil ic.*

meeting for such statements. Use of still, The pw:pOse of the meeting will be to motion picture, and television cameras..

'standard*plantdeslgns-lev~l c;iT design revi~w and discuss the following topics:, -. during this meeting may be limited to detail ( open}-The COmmiUe!l *wm

'

• The Committee will meet With the selected portions of the meeting as,..

review and comment' on the NRC Comriiissioners to discuss.items of

• detennined by the ACNW Chairinan.

.proposal regarding the level of design*

mutual interest (tentative)..

Information regarding the time to be set

• • .detail required.to Certify standar:dized

• The Committee will be*briefed by aside for this pUl"pose may be obtained

-nuclear power plant designs.

i:epresentatives of the Division of High-by a prepaid telephone call to the

. Representatives of the NRC staff a'ii.d -

• .'Level Waste Management (Dffi.WM) on Executive Director of the office of the the nuclear industry Will participate: is the results of their reviews of the study...-ACRS, Mr. Raymorid F. Fraley~

approp~ate.

Plans for characterization of volcanic (telephone 301/492c4S16) prior ~o the 3:45 p.lil.-5:15 p.m.: new s'tandard

. *features and mineralogy, petrology, and*. m~eting. In yiew of the possi~llit)r that.

- technical specifications (open}-A

• chemistry of transport pathways the schedule for ACNW meetings may briefing will be given by representatives * *

• .(tentative).

be adjusted by-the Chairman.as.*

of the NRC staff on actiyities to develop

• The Committee will discus*s the *

. necessary to facilitate the co*duct of the '

• new standard techni~ specifications NRC staff's ~tudy Plan..review plan. and*

oie~ting. persons planDing to attend

.

• for nuclear power stations licensed by staff plan for reviewtng the Site.-.

• should check with the ACRS Execiitive.

the NRC.

Characterization progress reports:

• Director or call the recording"(soi/492- *, *.

• S:lS p.tll.-4):30 p.i1i::'p~p~tion*.or- *

• The Committee will begin to 46oo) for the current scbed.ule if such ACRS reports to the NRC (open}-The consider 10 CPR part 60, high-level rescheduling. *would result tn major

..a*--*--

sed

• Co. mmittee \\\\'Ill UUK.iWNt. propo reports waste repository subsystem inconvenience.

.* to the NRC reg* ardlng cont8inment * --

performance requlremeiitil regarding their conformance with the EPA high-.

Dated: November 20. 1990.

. design criteria for fuhl;re nucl~ plants,.

level waste standards.

-John C. Hoyle,

• and the preliminacy t:lesign approvalJor

• .. **The Committee will bear reports Advisory Committee Management Officer.

the*Westingh.ouse SP/90 Standardized

• from its working groups on mixed

{FR Doc.~-Filed 1i-2.&-00; 8:4s am]

Nude~ Plan_L\\ * * *

. wastes, Carbon-14. and human BIWNG CODE mMWI fri~y; December 1, t!t90

- *

• intrusion.

• *Discuss and begin preparation for,.<<* : * :

• ACNW presentation at Waste

\\~:?:Advisory Committee on Reactor

, _ Management 1991 Symposium. Tucson; * ~-*~eguardsi Meeting Agenda * *

• AZ. Februaiy 1A 1991~.

. *.*. In accordance with the p~ses* of.

• The Committee Will consider a draft.: sections 29 and 182b. of the Atomic NRC staff Technical Position on.

Energy Act {42 U.S.C. 2039, 2232b), the Regulatory Considerations ln Design Advisory Committee on Reactor and Construction of the ~loratory Safeguards will hold a meeting on ShaftFacllity (tentati~e).-.

December6-8. 1990, in room P-110, 7926

• . ~e Committee will discuss.

No,rfolk Avenue, Bethesda, Maryland.,

an~~pated an~ propo.!Je4 Comnuttee Notice of this meeting was published in.

activities, meeting agenda~

the Federal Register on October 17, 1990.

administrative, and organizational matters, as appropriate. The members

• will al~o discuss matte.rs and spedfic

• issues which were not *completed during -*

previous meetings as time and availability of information permit.

Procedures for the conduct of.and participation in ACNW meetings we.re published in the Federal Register on June 6, 1988 (53 FR 20699). In accordance

• with these procedures. oral or written statements may be presented by members of the public, recordings. w.ill Thlirsday, December 6, 1990, Room P-110, 7920Norfolk Avenue, Bethesda, MD 8:30 a.m:-8:45 a.m.: chairman's remarks (open}-Tue ACRS Chairman will make opening remarks and coqiment briefly regarding items of current interest.

8:45 a.m.-12 noon: ITOL conversions for the Palisades Nuclear Plant and the

• Dresden Nuclear Power Station, unit 2

- (open/closedF-The Committee will review end report on the proposed

• 8:30 a.m.~11 a.m.: operatiiig expene~ce and events (o~n}-A*

briefing and discUssion will be ~eld _.

regarding recent operating experie_nce and events.at nuclear power plants, Including: experience relating to problems with the.operability of safety

• systems.caused by the egress of noncondensible gas: events at the Bruriswick plant relating to loss of offsite power and a main steamline.,

, isola~ion valve closlire at full powei:..

and a malfunction of the feedwater

- regulating system and subsequent failure.of the reactor core isolation cooling' system at the Pilgrim plant.

11 a.m.-12 noon: Future ACRS activities (open)~The Committee will

'discuss anticipated ACRS subcommittee activities, items proposed for consideration by the full Committee. and*

the scope and content of the forthcoming

. ACRS annual report to the U.S.

Congress on the NRC Safety Research Program and budge\\.

. l 493!i6 Federal Register./ Vol. 55, No~ 228 / Tuesday, Novembe~ 27, 1900 /.Notices 1 p.m.-2:15 p.~.: high-level radioactive portions of the meeting. when a...

• waste disposal (ope~)-A briefing and transcript is being kept. 8.nd questions The. agenda for the.s.ubject meeting*

shall be as follows:

discussion will be held with a may 'be asked only by members orthe representative of the Radioactive Waste Committee, its co_nsultants, and staff..

Wednesday, Deeember 12* l99G--8.:30 a.m. until the Conclusion of Business*

Management Board of the National *

. Persons desiring to make oral * *

• Research Council regarding the National

.. sta:tementnhould_ notify the.ACRS The Subcommittee will discuss the Academy ofSciences/Natiorial Executive Director as far in advance as status*of*the NRC staffs program on Research.Council report on "Rethinking practicable so that appropriate *._,: * *: *

.interfacing systems loss of coolant High'..Level Radioactive Waste*

arrangements c8n be made 'to allow the accident (ISWCA).

Disposal..

necessary rune during the* meeting far,

. Oral statements may be presented by 2:30 p.m.-3:30 p.m.: NRC ~afety

• such statements. USe of still. motiOn -:* :* :.-.

members Of *the public.* with the-research on seve~ accident scaling

• picture and televisidn cameras dmmg :,.

• concurrence of the Subcommittee :. *

• methodology (open}-A briefing and this meeting may_be limited to selected Chairman; written statements will be' discussion will be held with Dr. N. '* _.....

portions of the mEleting u ~~ed*

accepted and made avBilable to the.* *

~uber, NRC staff, regarding.

• by the ChBirman. ID!ormation reg~ding Committee. Recordings will be penm1ted

• development of a scaling methodology *

. t!ie time ~o be set asfde for, this. purpose

. only d\\Uing those portloiis of the for direct containment heating.

may be obtained by a prepaid telephone meefin8 wh~ a ~aipt iS being Lipt, experiments...

c8ll. to the *ACRS Executive Director. Mr.. *and question& may be.&abd orily by *

• 3:30 p~-6 p.m.: preparation of.ACRS * ~

F. Praley..prror. IQ: the nieefin.8.

members ofthe: SubcGlinmi~ itB....:

reports lo. t!ie NRC (open}-The

• .* * *

• In vie\\v of the possihflitf!ffiaf *tJie. *... * :: * *consultants. and staff. Per&Ous desiriDg :

Committee will discuss proposed ACRS scliedale foiACRS mee. t;..,..,._.l!iaf. be*:'~;:. to* make oral atatemenb abould-...i'-.

• reports to the NRCnigarding additfoDal adJairted bj the.~~

ne~llsmj.. the ACRS staff members named bei~

• certification fssUeil for evolatfonmy ::..

to fadlitate*tht! condUctofthe mee~. as.far in aav.ance aa:IS.practfcable sO.,_,..

ligbt-wate~reactOrs.' and contahuneiit persons p~*t.o' iittend ~otilch:heck. : thataplJl"Oprlate anailgeinents Cari be - **

designcriferiafor.~ptan.u::.,,.* ! ~-*;;

wfth'theACRS.ExeCUtlve.DtreCtcitif *:.

• made ' * :. -"'*..,. **.,,,.'::, *,- '*.-'*

Saturday, December~~*'**:.:.!':: ::..... ~.,

such.res.c{iedulingwould~sultlnmal~ *. ~~initi~i~~ofthe.::. :

....,~--~*"'

tnconV~en~..* _.........,._.,,..,.., :**J.

mee"-"-'theSubcoinmittee;-alonawith*

8:30 a..mr.Ba.m.: 'election. o' ACBS -..

. Iha. *- "de*

. ~a\\.:.* *, ~ *1,:,b;:-.i-::-_-:r.i

~fl'- __ :..-i£_._* -L.:.-.;

-obe ~.. -.:-

.'.I ve

~ *~~ce

WJ.W

• any o..., ""~UWUW!.wuu ~. *' *

• officers (opeii/c/osed~Th.e ColDllllUee subsectttm iO(dJ Public:.Law*DZ-463 that *- present, may exchange preliniinary.'=.: *-

.

• willelectJ\\9RS ~ffi~for.CY ~....

it is nece~.fo'-~~na otthiS *:

• *vie'Ws~matteni teibe).,,,*;****

.. PortionaOf'this.sesaion will be closed

• -~1r... *

• .*.,.~. w.._....,;.....r._.:.;.'....::..*--**"" **.. *;_:__.~A...&......,..;. ~-1..,;;;. * "'L.ir.a..~::,...

• asneCeasa:rytodiscusS'lnfOnii&.tiOnthe. ~~~0~.,~~~~"*'P':'Zil°'~t!~.!*.. :;ir~*: '-~~~~~~c:-'~,~*:;.

• rete. aseofwhfch*w* 0*u1drepre* sen* t.. ;.-...,.

ProPi'.fe~&UWrmij.lfOD.appw;aomfO,,.

meeting.~t'**-.,dt!..,rvl"J!."S: :~~.:.. '. '.;..... *.

~~,. *! *

-themattenf'l>efntC:onaidered.(5".U'.S.C.:~-. *. TheSubCOmmluee1villthedlleat-';~-;_*.

clearly.unwarranted~v~.of ~*.. *.

"'""""-~* * )(""*i-~

.:;;~.LO::-.J.;..;.* __..:..r..,..

~...:....~

dL~1..a.M..;_...;fo*-..10

• pemouat~. * *¥**...,

v.u.uc..,,1o&U&orm8wuu,aw:,.__..... :..

presen---ur'BD llVIUUNl'iUIRt g a.m.-t~a.m:/1/rep~Uon 0j.":*.~*0_ _. whl

~ouldrep~en~an.~Wa#Ant.~

with ~tatives:of IUNRCBtaff::*:

-ACRSriijwrts*totJieNRC(o~):;..The *...

fnv~onof~Datpriv4CJ@:~G.r. 1 *- theirconsultanls.'imdotlia.hiterested"...

• Comnifttea'wilrdisfuiprop~ieports

• S52b{c](6)) ~

~~ati~ ~~

~".o:fves

~-regm~thls~~,,;:1.?*~=-'<'.~'.*

-: to NRC ~

fteins*Consfdeied the internal pe:rsomiel ro!eir an4 *-.. ~~*~* ~ *... ~er information regarding fOpfcs :

~. d~. thi9 m'.'eettn8..&Pd m_atters w~c:h,;:. : :* practices of.1!1~ ~~cy-~5 ~~~

1

-*~:?!~~1: *.. to be di.scussed. the ~e~

of.. :*: i were not compfeted'at'~o~: : '.'

552b(c))(2}):....,.. _... _,,_ _,_,.,r.'":*'._.. :.. **::.:* **

sessi~.open ~o-the'pub~~~~~~~'

meetings as time *and avaIIabUity'of..... Further lnfmmatfon tegardiDg topics* t *.. m~ting bu~

c:ancell-:c! ~ :-* ="::

. informationpef1?l._ ;~~"'~-'~..rj~,t*l ;::o~r*<'I to be discussed,wheth~ the meting.has. :. res~eduled; th~ aia&iruia~riiling ~ *..

11:30 a.m.-12 noon: appointmezit and*

. been c:ai1celled ouescbeduled. tha....:;-"-. *. requests for the opportunity to*~*'

as8igninen1So/ACRSmembenJ(OjJen/.*

_Chalrman's~~~~qu~i;f for~~:*':. orafstatenients_and_~tim&allotte<r' -*

• closedf-The ~tee'*wnt discuss the. opporfunily to~~~~~~

.* therefor:can*beObtatned 11)' a"piepaid'-_:

status of app0intmentofcan<;Udatet1 for

• and the timealfoted can be Obfafned*~

• telephone-C&Jl Cc>. the~a(ed F~

membership on* the Committee and * ~.-..

a prepaid teleph~~ can to~

J\\CR~,.

Official. Mr. Paul BOO!mert (telepbOne :

selection of ACRS *membenr for related'*

• Exe~ve ~~

• . w... ~~.f

~i,;:;,,-,

301/49z:.8558} between.7:30~"!

~ ~n<r..

• as=r~ss~~~!~~:*:;~~ =~~~~~1J~[!,~' ~"!:N:=fr!==~

as necesliary to discus!J fnf<)nn8.tioo.the Dated: November ~UOO.:i*:;;. ~h.~, ::l._,\\... :'.;-.. : named*individual ~'or*~

~a~-:~': * *,

releaseofwhicbw?uldrepresenf'm-. _;;

JolmC.Hoyle.;.,., :\\.t~~; -~:...; ~J.:.:!'.')-'.

• bef~re.the scheduled ~tmgfober. *

• unwarranted in:vaS1on of personal * *.

Advisory. Coinmittee lr!0nageiilent o/tfCer; ~-.. adVISed ~fen_Y, changes. in ~-~~\\etc.,

privacyandfutemalpersonnelrule&*and

.r.:...:...

- *,0 *,

,'/::. whichmayba~oct:tJri'ed;"*'..... * * * *.*

• cti rth**

[PR~00-27780F'l...-ut1-26-90:a:4S~I *.

........ *~::;.,;*.:.*~..,.. :

pra ces.o e.agency *. - ***-*'": *:*****-*

'1~:-.:.:;:.:*,:.;:::.i.;<>*, 1;!.

• Dated:Novembet19..1990. *-,... *.. * *

• 1pJn.r2:30p.rn.:.miscellanous:"' * :;:*

BIWNGCOOE~Mr.

• .. _..:i..:.:.n:.._........... -*": '* * ~*

.... "-.*:,~.., -*'" *-..f*

GaryR.Qui.*.............,.r... _........... :

. {open)-TheCommittee will complete '*

C'h *. f.*"' -~* Re....

• 'Bran

..,_L-*.~-

. discussio!1 *of items considered. d~. ':..

• AdvlS~ri ~'hi.~ltt~~~~ R~~~~~'~:. -~~~-~ " * * ~'ti=~&

'fu'~ 11_2:~;.:~~-~~l'. :.'

this ~~anditems of an.*'.::-.:*:**'*" - Safeguards;SUbecirifnttttee'onThermal......

adminisfn!tive*natute a~ appropnat.e~

Hyctrauffe Phen0mena; Meetfilg :-. *.> '.'.;.. t;i*LllffG ~.

7590-01-ll ** :-. '* >' ' ';:'.: *..:

• Proceduresfortheconduct.of.an:.

parti.cipati?n in ACRS mee~s-~ere: :.. :

• The A~

Subcolnmit!ee oi:i Th~~l_*.. AdvlSOrY Conimrttee-O&:l Reacfor..

published rn the Fedenil Register: c;>n *:.::

• Hydr.aulic Phenomena will hold a,**:* *.* * *

• 1... Safeguard~ Subcomn\\ittee on.

October 2,. 1~ (Sli FR 40249). ID -.,~,,-:;-(

~

meeting on Decemtier 12.. ~

~ the*** *.

Plannrng and Procedures; Cancelled

. accordan~ with. these: procedures,. oral

• Delaware RoOm at the Holiday Iim. 8120 or writteri.statements may be presented.

Wisconsin Avenue; Bethesda; MU;.;'.:.*

The Subcommrttee*meetirig Ori" by members o[tbe public,. recordings.. ;

The entire meeting will be*opento* *.-'

Pla'nning.and Procedures schedaled for will be permitted only during those open public attendance. '.

. December 4:1990. 3 p.m.,*room P-422.

~

• /

\\I UNITED STATES NUCLEAR REGULATORY COMMISSION

• .ADVISORY COMMITTEE ON REACTOR SAFEGUARDS.

WASHINGTON, 0. C. 20555 Rev. 1:

November 28,. 1990 SCHEDULE AND OUTLINE-FOR DISCUSSION 36~TH:ACR~ MEETING

_'DECEMBER 6-8, 1990 Thursday*, December 6, i990, Room.

P~110.* 7920 Norfolk Avenue, Bethesda,.

~--

1) 8:30 8:45 A.M *.

2f *8:45 12:00 Noon (10:30-10:45. -

Break)

I

~*

12:00... -

J,.:30 P.M *.

3) 1:30 r 2:30 P.M.

2:30 2:45 P.M.

Opening Remarks bv ACRS Chairman (Open)*

.1.1}

Opening.Statement (CM/GRQ) 1.2)

.Items of *current interest (CM/RFF).

FTQL =conversions. for. the Dresden-Nuclear Power Station Unit 2**and the Palisades

..., Nuclear Plant (Open/Closed) 2 ** +)

Comments by AcRS* subcommittee

- 2.2) chairman (CPS/MDH/HAl Meeting: with represe:ntatives of.the

-NRC staff and the _licens~e (Dresden Unit 2)

_2.3).

Meeting with representatives-of the NRC staff and the licensee *(Palisades Nuclear Plant)

(Note:_. Portions. of this s'ession will.be *

• closed as *necessary to discuss Proprietai:y Information applic~ble to the nuclearuhit

.being considered.)

LUNCH High-Level-Radioactive-Waste Disposal

{Open)

• 3.1)

Comments by designated ACRS member (HWL/EGI).

3.2)

Briefing by chairman* of the.National.

BREAK Research Council Boa_rd on Radioactive*

Waste Managem~nt on the report entitled, "Rethinking High'."'"Level' Radioactive Waste Disposal"

. l 4'}

. 2:45 4:45 P~M.

5) 4:45 6:QO P*M~

2

• certification.of standardized Plant Designs (Open) 4.1.)

comments by ACRS s~bcommittee*

chairman regarding the level of design detail required for cer-tification of standardized plant designs '(SECY-90-377). (CJW/MME}

4.2) >. Meetil)g with* repres~ntatives of the

'* NRC staff and.the nuclear *industry (NUMARc').

Preparation *~f AcRS Reports to NRC (Open).

5.*1}

• Containment Design Criteria for Futµre Nuclear.Plants (DAW/MOH)** '.

5.2)

• .. Preiiminary Design.Approval. ~or the*.

WestinghouseS/P 90 standardized

... P~ant.Design (JSC/TSR)

Frid.ay, December'?, 1990*, Room P-110-, 7920 Norfolk Ayenue, Bethesda, Md.

6) 8i30

- 11:00 A.M~

(10: 00.;....10:.15, -

Break)

7) 11:00 12:00 Noori.

4!.

12.: ob 1:00 P.M.

• Nuclear Power Plant Operating Experience and* Events '(Open}

6.1)

Gomments *by ACRS. subcommittee."

chairman.. regarding recent operating*

events (JCC/PAB) 6.2}

Briefing by representatives of ~c.

Staff.

Future ACRS Activities (Open) 7.1)

• Anticipated ACRS subcommittee.

_.7. 2) 7:3) activities.. (RPS/GRQ) '*.

Items proposed for consideration". by"

• the full.commit~ee (CM/RPS)'*

Preschedu1ed meeting dates for meetings with--}:lRC Commissioners

,,. (CM/RFF).

• 7. 4).

Format. and content of the annual ACRS

• report-to the U.S. Congress on the

• . NRC Safety Researc~ Program (IC/SD)

Ltm,CH

• • • r

8) 1:00 2:30 P.M.

2:30

-2:45 p.M.

9) 2:45 4:00 P.M~ -

10) 4:00 6:00. P.M*.-

3 New'Standardized Technical Specifications (Open)

. 8.1)

Comments by ACRS sub_conuni ttee chairman regarding the status of NRC staff efforts to develop new standardized technical specif ica-tions for nuclear power plants

" (JCC/PAB)

.8.2)

'- Briefing by representatives. of the NRC staff '

• BREAK HRC Safety Research Proaram (Open)

9. _1) *

• Comments by ACRS subcommittee * '*

chairman regarding research related to development of a scaling methodology for direct containment' heating phenomena (IC/MDH).

9.2). *Briefing by representatives of the.

NRC:Offic~ of Nuclear Regulatory

• Res.earch

• I' Preparation of ACRS Reports to the NRC (Open) 10.1) 10.2)

10. 3.)

10.~4) i'o *. s) **

10.6)

Additional certification issues for_

evolutionary light-water reactors (JCC/MME)

Containment Design Criteri~ for Future Nuclear Plants (DAW/MOH)

• _

FTOL conversion t:or. the Pal:lsades *.-

Plant (CPS/MDH)

FTOL conversion for the Dresden-2 Nuclear Power Station (CPS/HA)

Westi~ghouse S/P 90 PDA (JCC/TSR)

Levei *of Design Detail (CJW/MME)

Saturday, December a*, 1990, Room P-110, 7920* Norfolk Avenue, Bethesda, Md..

11) 8:30

- 9:00 A.M.

Election of ACRS Officers (Closed) 11.1)

Election of ACRS officers for CY-91 (CM/RFF)

(Note~ This sessio~ will be closed to discuss *irtformation the release of which would represent a clearly unwarranted inva~ion of personal ~rivacy.)

.i 12).

13)

• 1:

14) 9:00 11:30 12:00 1:00

-11: 3.0 A. M.

l~:OO Noon

• 1:.00 P.M~-

• 2:30 P.M.

(

4.

Preparation of ACRS Reoorts to NRC (Open) 12~1)

Discuss proposed reports to NRO regarding items considered* during

• this meet'ing

• Appointment.and Assignments of ACRS Members (Closed) 13.1).

\\ Briefing* regarding the status of*

'* seiection/appointment of* new*

members (CM/MFL)

.13

• 2)

Activities of ACRS menib~rs ""."

• ACES.

• member on RES Peer Revi~w Group (WK/RFF)

(Note: *This session wi,_11 be, closed to

• discuss i,nformation the.release o~ which would represent an unwarr~nted invasion of personal privacy and.internal personnel rules **and practices of the agency~.>

LUNCH Miscellaneous (Open}

14.1) -Complete discussion of considered during this; administrative matters

. /'.

l I

.items meeting an4 as.appropriate

'.,,~

L \\..

'**~.

J.

J' 1*

• -~

.,_\\*

-MINUTES _OF THE 368_TH ACRS MEETING_*

DECEMBER 6-8, 1990

• i.-

• The 368th meeting of the Advisory Committee on *Re~ctor Safeguard's (AC~S) was held at Room-P-110, 7920 Norfolk Avenue, Bethesda, Md.,

on becem;t:>er 6-8, *1990.. The purpose of this meeting was to... discuss -

.. and: take:' appropriate. act-ions on.the ite_ms listed in the a'ttached_

agenda., The entire meeting was open to pUblic attendance,* with* the*

._. _exception of portions that deal t'-wi th tJ::i~ election of ACRS off ic~rs

-*and.'discussion... of the qualifi9ations of candidates for*_app_ointlhent to** the A.cRs.,,_ *

- A transcript of select,eµ portions of the.me~ting ~.as *kept_,and is _".,: ~- :.. :,. -

available in the

• NRC, Public : J:)qcument* _Room*-.

(.Copies.*.'.of the. " * *.,,

transcript are.available for* purchase from_ Apn Riley.& _.Associates-;

Ltd., 1612 K.-Stre~t., N.w~, Wash'ingt;,on*, o.c.* 20006.') -

• ,ATTENDEES.

ACRS-- Members:

c. Mfchelson,(cha:irmatj) ~:

• c. J-*. Wylie (Vice*~... -_.

Chairman), _ J. c. -"Ci;irro 11., _ I

• ca t'tori ~ w. :Kerr, "

.: H_._.w.: Lewis;- P. G~- SheW!nori, c.~ P.* siesst *D.* A~*-

• Ward, and J_ *. E. Wilkins*:

\\ -

• ,' L' I~ *

~ -T/. Chairman* s Re1;>or't

[.NOTE*:. Mr. R... "<-F.

F'r~-ley *w~s th~ 6~sign(3,.t~a Feder-al'._ off~c'ial_ for: /.'.--..

this p9rtion of *;the _meeting.' j *

• \\' _*

I,.*

'*'T'

• -Items*- of* curreri-t Interest

.. Mr. _:Michelson ~nf 6~ed: the members-th~t -Mr;. M-inriic~ had subinitted. -<

_*"his-resignation due:* 1'.:o _health-related. prc;:>blems.

, ~.

_II~.,:._ Full Te~ operating License (FTOL}. conversion for th'e Dresden*

Nuclear -.Power s*tat*ion,* unit 2 *

[NOTE: -

Mr *. H.

• Alderman was the Designated, Federal* Official' for th~ portio~ of the mee.t,tng. ]

Dr. Siess, Chairman of the F_TOL. Conversions Subcommittee, stated in his opening remarks. _that there were si~ plants that had' to *have provisional operating licenses* (POLs) converted to FTOLs.

• The ACRS.

~ reviewed FTOL conversions for Robert E *. Ginna in 1984, and for Miilstone, Unit 1 in 1985. Besides Dresden-2 and palisades~ Oyster Creek and San Onofre-*1 remain to be_ reyiewed -by the. ACRS.

., <<* ~

. j.-

-~

368th ACRS Mee~ing*Minutes 2

Presentation by the Office of Nuclear Reactor Regulation CNR~)

. Opening Remarks' -

Mr. J. Zwolinski., NRR Mr.. J.

Zwolinski~ Assistant Director,

• Regi~n. iII *Reactors 1 NRR,

• stated.that the staff would present an overview of the POL-to-FTOL converi;lon process.

He noted that Mr. Cordell Reed, Senior :Vic~

. President, Commonweal th Edison *company, would. discus.s the Dresden Facility and the Commonwealth Corporation, and 'that Mr.

Joe Eenige11burg, Plant Manager, Dref::!den, woµ~d-address plant operating experience.

POL-to-FTOL conversion Process -

Mr. :B. Siegel, NRR*.

. Mr.

_Siegel,

NRR,.?iscussed the past history of POL-t6-FTOL conversions.

He noted that:* there were 15 POLs issued by tl;i,e. Atomic Energy Commission.. The normal procedure was to convert 'the' POL to**.

an FTOL after 18 months of operating experience. In 1970, there

.was a rule cQ.ange that deleted the issuance of, POLs~ This created a situation.where there was riot a mechanism for conversions from.

POLS to FTOLs*.

. *In.*' 1977, the. Co~ission ado.pted. a staff

. recommendation that the POL **plants* be incl~d.ed in* Phase II of the

_Systematic Evaluation. Program. (SEP).-.-

The.SEP. review had to. be cqmpleted before.the.-staff *could issue an FTOL...

I Mr. Siegel *stated that Dresden-2 is* identical to Dresderi-3 *.which*

has an FTOL.

T,he only significant difference between *Dresd~n-i and Dresden-3*. is the fact that: l;>resden-3. replaced the recirc'ulc:ition piping and DresdE:fri.,.2 *did not.

SEP Open Items Mr. s.i(!gel, NRR

• Mr. Siegel' NRR; stated that there was 'only one SEP 'item,* related' to classification of structures, components,. and systems, that remains to be resolved.

This. l}as to do *with the : service-level -~

temperature and fracture toughness of the-materials'that.were used in. the plant and whether or not: they have changed from* the :time the plant was originally designed.. 'This issue is. in the process of resolution.

TMI Open* Items Mr. Siegel, NRR Mr.* Siegel discussed briefly the status of.impl~mentation of TMI items:

Detailed control room design * -

Questions still remain regarding the annunciators. The main problem 'is lack of time.

• The work can only be done during a refueling outage.

v.

368th ACRS Meeting Minutes _

3_

Instrumentation for detection of inadeauate core cooling -

Thi$ issue will take two cycles to complete, one cycle to make the penetrati'ons and make measurements, and.the second cycle to.do the installation.

Upgrade of.emergency preparedness - This issue deals with the utilization of an improyed

'model for calculating

• meteo_rological data.

Post--accident monitoring instrlimentation -.... This*,issue deals with the installation of neutron flux monitoring instrumen~a-

-tion that -meets - the requirements of.. Regulatory Guide 1. 97,.

"Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess* Plant and Environ Conditions During. and_ Following an Accident,"

and 10

• CFR Part" 50.. 49,

• "Environmental Qualificati_on of Electric Equipment Important to Safety for Nuclear Power Plants. 11 Dr. Shewmon ~sked-whether cracks could-be examined through a weld 6veriay~

Mr. Eenigenburg, Commonwe_alth Edison, *said that* tpey could.

He* stated *that the weld ~overlay is*; inspected for. crack, propagation *_into the overlay. * *

- /"

Unreso/Ived Safety Issues CUSisl

.Mr. Siege_l, NRR

/

• I Mr. Siegel prqvided the status of impiementation of usrs:

Anticipated Transients Without **scram CATWS) * ~-

Mr.. s_iegel -

stated that the ATWS issue is generic to almost all-.the -BWRs_.

It. has to do wi~h diversity associated with the alternate rod

• injection arid reactor pump-trip.

• The BWR owriers Group-and. -the staff disagree OJ:) the. resolution of this 'issue. *The Owners Group brought this matter to the attention or'the EDO, and the EDO tooR a -position that the liceniee ~hould p~ovide diverse

.alternate trip units.

Station Blackout -

The licensee has agreed* to put

• in* a

• nonsafety-grade fourth* diesel generator that can handle-the loads for -both Units 2 and 3 in the event of :a total station blackout.

.seismic *qualification of eauipment in operating plants - The specific requirements and 'approach' for implementation. are

• l;>eing developed jointly by the staff

-. and the Seismic::

Qualification Utility Group.

Safety - implementation of control systems submittal is under staff review.-

The -licensee 1 s

1.,

368th ACRS Meeting Minutes 4

Hydrogen Control ~ The staff's position is ~ha the licensee does not meet the requirements* of 10 CFR Part 50.44, "Standards for Combustib~e Gas Control System in Light-Water-Cooled Power *Reactors."-* This is under* discussion between the staff anq tne., licensee.

staff Conclusions -

~r.' Siegel, NRR Mr~, Siegel stated that bas~d on its, review of the information su_bmi tted by the

licensee, the staff has reached..several

• conclusions, including the followinc;r:.

The licensee is technically qualified to engage*iri activities authorized by an FTOL......

• ~

~.

,~

Dresde~-2 has had 20 years of successful oper~ting experience*._ '*

~issuan~e *of an ".FTOL*will not** be inimical to thk common* defense and_ s*ecur'ity or the *health and safety of the P\\lblic. *

• Dresden-.3.;. which is *identical to ~i:esden-2, *has been *fssued

.. an FTOL.

• The $taff recommends that an FTOL be issued f 9r Dresden-2...

.,1.

There was-some_ discussion about the phrase. that* the qpe~ation. of t.he. plant can **be conducted "without endangering the h*ealth and safety of the public*i 'versus -"without undue risk to the heal th and safety of* the public~*n The conc~rn was that the.first phrase* does not indicate any risk at all..

Mr. Siegel indicated that the staff's phrase comes: from 10 CFR Part 50. 57, "Issuance of Oper~ting

• *. Licens~.... This comment was not.resolved.*

. *'MRC 'Staff's Pe~spective***~n the Cp~rat:lng -History of Dresden-2 -: Mr.

• Siegel, NRR Mr.

Siegel. provi~ed the -staff 's perspective history of Dresden~2:

' on the' operating Dresden Units 2 and 3 were.put on the watch list in 1987 based on th.e results of safety *system outage management inspection

.-and diagnostic evaluation: testing, and also as a result of many

scrams, poor radiation.

protect~on and maintenance practices.

~h~ licensee had recognized these problems in 1986 and had started taking corrective actions which included management changes and improved maintenance programs directed at plant

~afety and performance.

368th ACRS Meeting Minutes 5

Since October 1987, Dresden has demonstrated sustained good

.plant perf ormancie ~

The number of scrams, engineered safety feature actuations, and human errors have been reduced significantly as a result of improved programs ~nd management*

involvement.

Presentation by the Licensee -

Mr. C. Reed, Commonwealth*Edison Company Mr. Reed noted that the modific~tions resu'iti11g from the'SEP*were made. not only

• on Dresden-2, bU:t also on Dresden-.J*

• and Quad Cities-1 and -2.

He pointed out that Quad Cities-1 anq -2.. have a two percent cleanup system versus a* seven, percent system

• at Dresden.

The* result is that* the radioactivity le~els at Dre~den are lower than at Quad cities.

Mr. Reed noted that they were *pleased with the progre_ss they hav~.

made in improving plant performance...

Operating History - Mr. J. Eenigenburg, Commonweal th Edison ~ompany Mr.

Eenigenburg stated. that after** repognizing in 1"986 that' improvements were necessary, the corporate self-assessment progr~m.

was developed.

Since development of. the self...:*a.ssessment p;rogram, several improvements ~ave been made:*

Significant improvements have been made... in the area of in-service: testing.

.r*.

Emergency operating* p~oc~<;iures have been upgraded.

The ~aintenance area h~s shown significant improvement.

Record runs have' beer\\. made by.both units.

Dresden. was recognized by.the General Electric Company for operating for, 403 days without a reactor scram on either unit~

. The training facility is almost complete.

The site-specific simulator will. be operab_le n.ext year.

• Several physical. upgrades to the plants have b.een made.*

The *radwaste system has been upgraded. significantly~

. The Systematic Assessment of Licensee. Performance

( SALP) ratings have shown significant improvement.

The forced outage rate has diminished.

Personnel error rates have diminished.

368th'ACRS Meeting Minutes 6

The amount of radioactive waste ":shipped_ off-site has diminished.

Personnel error contaminations show a significant decrease..

. The Committee provided~ report to the Commission on this matter as discussed in Section I~ of tQis.document.

III.

FTOL Conversion for the Palisades Nuclear Plant

[NOTE:

Mr. D. Houston was the Designated Federal Offfc'ial for this portion. of the meeting. j*

Dr. Siess, *Chairman of the *FTOL Convers'ions Subcommittee,.. stated th~t.this po.rtiori of the s~ssion was in regaJ:"d to an FTOL for _the' Palisades Nuclear Plant. *'He said that copies of the. staff-' s Safety Ev.aluation Report (SER), NUREG-1424, related to FTOL conversion for Palisadcas have been provided to the Committee..

• He stated that

• _Palisades is the first large Combustion Engineering (CE) nucl~ar plant and uses one* of. the *very.. early. prestressed conci;-ete containments.*

NRR Presentation* -

Mr. Mascia11tonia/Mr. Holian~ NRR Mr. Mqsciantonio,* Nim, discussed the staff's review. activities

• associated with the FTOL.conversion for Palisades.

He presented a brief description of the plant, a chronology* of -'the license applications and issuances,. and the highlights of, operating.;

history~ He discussed the review performed* as part of the SEP and the current status of the three outstanding issues that were not resolved *at. the time.of the previous ACRS.meeting.on this' matter*

in 1983.

He discussed. also the status o_f the: usis of which six are currently not implemented.

Dr. Shewmon asked if the SEP issue.related to pipe breaks inside containment had been resolved by the leak-befor~-.break* ai::gum~nt.. :

The licensee indicated that it was.

Mr. Michelson asked whether this review ~was performed in accorda;nce with the latest Standard Review Plan*(SRP).

The *staff was unsure that the review met the latest SRP version and indicated tha~ they would look into it.

Stating that the CE Owners Group has indicated that USI A-4 7,

'.'Safety Implications of Control Systems," is not a safety issue, Mr. Michelson asked the staff about the current position of the CE Owners Group on this matter.

The staff stated that the.CE Owners

. ~' *.

• • \\*

I

.. 368th ACRS Meeting Minutes

• 7 Group position is still under review.

They ~greed to forward.the ACRS a copy: of their SER on this issue whe~ it is.completed.,

• . In response

~o, an inquiry by. Dr.

Shewmon,.. Mr.

El 1 iott, NRR, discussed the current position. at Palisades in regard to the revised Pressurized Thermal Shock. (PTS) Rul.e.

The plant "will bump up against a screening criteria in the.year 2601 unle~.s flux is furtper reduced or a more sophi~ticated analysis is.performed~

1 *. Mr. Holian,' NRR,. discussed two of* the.* current* plant-spec*i~ic.

• . ac~ivities at Palisades. "*The *first of these was in.regard te> the**.

• replacement.of the steam generator~* The old st~am gener~tqr*was cu~ away fr.om its piping and taken out through a large hole cut

• into the concrete. containment.

The steam generator has.* J::>een*. put

. *in place and the patching of* containment* nearly* comple.t.ed. : The second activity was in-regqrd-to new plant ownership (pending F;ERC.

. approval) with the following bre(lkdown:

. Consu~ers Power * (44%),._

'. Bechtel.. ( 3 3 % ). and West.:lnghouse *c 2 3 % )

• Under the. new,_. arrangement, Consumers. Power* would still have the sole re*spcirisibility for*.*

operating the plant.

Mr. Hollan concluded his presentation with a discussion of the results of 'the last. five SALP *reviews related to Palisades.

Licens'e~ Presentation -

Mr. VandeWai1*~, Co~sumer.s Pc:;>wer. Company Mr. Vandewalle, Consumers Power Company, -di*scussed briefly* the organizational *structure within Consumerf:? Power and. the plant, operating history,.. major modifications, and a r~cap of the steam generator replaceme.nt* :Program~

He.. stated that the. mission *at *..

Palisades w~s to ha~e it recognized.as one of the ~op ten _plants*

in the u. s *"

To do this, they want to be *rat~d in the top* quartil.e in. each of the -.nine areas. rated by INPO.. Regarding.. the steam generator replacement, he indicated that the'project is about t.wo

.. weeks ahead of.sched~le (-22 weeks total)..and that worke_r 'exposure has been significantly lower th.an predicted (expected to finish

. below a tot,al exposure of 400 p~rson-rems) *.

After further *deliberations, the Committee provided 'a report to the Commission as discussed in Section IX of this document.

IV.

High~Level"Radioactive Waste Disposal (NOTE:

Mr..-E. Igne was the Designated Feder~*l Official for this.

~port~on o~ the meeting.]

Dr. Frank Parker; Professor., Department of Ci vi*l and Environmental Engineering, Vande.rbilt University, and Chairman of the Board ori Radioact,tve Waste Management, National Rese~rch *council, at the invitation of the ACRS, briefed the *committee on* the National

• ~*

,368th ACRS Meeting Minutes 8

Research Counci*l I ~ report entitled."Rethinking Radioactive Wast'e*

Disposal," dated.July 1990.

Mr. Michelson noted that although, :the ACRS is not involved 'in the high-level radioactive waste* ~ispbsal*

.review per se, it has *a very strong interest l.n being informed on this. matter.

The major issues in Dr. Parker's presentation are listed below.*

Based on its *review of the.. Department of Energy's report *()f 1985 related.to the ~igh-level waste siting selection process, the*Radiation Waste Management Board of the National*Research Council stated:

"The methodology of comparatJve assessment is.unsatisfactory, inadequate, undocumented

• and biased,. and

. should *.. be r*econsidered."

The Board and* *invited worldwide experts met on their 9wn initiative in Santa-Barbara in July 1988 to survey past and*

preserit programs on high~level radioactive waste disposal and to *formulate: guidelines on *the inethodology of comparative*

assessment.

The *. outcome of th:j..s meeting was.

• the rep.art e11titled *11Rethinking High-Level Radioa*ctive Waste.Disposal_."

The Board **finds that the presen.t system facilitates* rigqrous

• oversight and technical auditing;* the _goals and standards are..,

clear.

It creates a sense o~ confidence in planning and.*

operation of the repos.itory and, if :carried out according to the specifications,. it would be robus.t in. the face of.

administrative and legal ch~llenges*. However,. the Board find_s that the *present approach as outlined in* the legl.slatio'ni regulations, and in practice is almost certainly doomed.to

. failure because of its.high* degree of. inflexibil~ty.. with; respect to both scpedule and technical-*specifications.-

The* Board believes that the present 'program is not a sqcially

• satisfactory resolution of the problem* for two m~in r_ea:son~:

The n,exus between nuclear energy* and waste disposal:

The flaws ahd* faults in the* U.S. program..

The performance criteria with respect to collective dose~ are unique to *the U. s.; all the other countries use risk or individual dose.. Also unique to the t,J.s.* are the criteria for barriers. The Board believes that these perfO'rmance criteria*

do not necessarily protect. the *human

.bein~s

• and the

.environment.

It was noted that criteria of other countries address* protection of human beings.,

A-"~. '

• ..J.**

' 368th ACRS Meeting.Minutes 9

Major findings of the Board include* the following:

.~.

Modeling should be used to comparoe realistic.alterna:tives.

and should not be a. debate. on *absolute safety. *At the present time, geological models cannot predict precisely what will take place in the future; large uncertainties exist, and absolute *safety or zero risk is nonexistent.

Computer modeling tecpniques can and should have a key role in th'e. waste* disposal assessment.

However, geophysical models are being used to predict,.the detailed..

behavior,of sites over thousands of* years~:*

The Board *

. believes that this. is scientifically unsound. and will lead to bad engineering practices.

t There is universal agreement that the.present generation should be responsible :for,the waste prodµcts since they l)a've reaped the.benefits of those wastes.. It is* also a fact that radioactive waste lasts for an.extremely long*

period of :time' and that the r.isks of high.:..level wastes

• will be felt yery locally (one or two ~ites in the lJ. s.) *

. The Board stresses fair process<.:....;. people feel threatene'd.

by radioactive:* waste and need*tO. b.e involved in deci*sion.:. '*.*

making, especially _in the*.location of -the repository or*

.. siting.

The *search should not be arbitrary

• but should be objective,.. scientifically credible, and procedurally:*

fair.

The public must be taken* into.the.process or else.**

It.is.doomed td failure.

. With r~spect to instilling confidence in disposal or how

.: to build that tr~st and confidence,* the *Board.. suggests:

Remoteness to dense *populati9ris ~*

• tonservativ~ engineering design~.

• Mat~emat.ical modeling.

Performance assessments.

Remediation possibilities~*

Expert opinion.

The B6ard believes ~hat ther~ are scientific reasons to think that a.satisfactory high-levelwaste repository can be built. and iicensed, but. also feel*s that the current u.:s. -program s.eems unlik~ly to *achieve that desi;rable,

goal..

The Boarq suggests an'. alternative approach that.

• is more flexible, uses a scientific approach, and employs

, modeling tools to identify areas where more information is needed, rather than to justify decisions that hav~

already been made on the basis of limited knowledge.

l' 368th ACRS Meeti'ng Minutes 10 Dr.

• Kerr. *stated: that the existence.* of.. ;Large

• database

.and s6phif,>ticated *computer models* suggest eri*oneously. that. it* is

• appropriate to design> a geological repository _as if it were a nu.clear power plant or jet airplane, both of which* have *pr~dictable

. attributes over short lifetimes~ Dr. Parker* agreed and S?tated that

• reiati ve to the. matter. of:_(_ a geological, reposi to:ry, __.Dr. Kerr's analogy should have. peen* included in the repor_t.

Dr. Lewis asked. how the report"was received.

br.. Parker stated***

that t:he Board,did not *realize the extraordinary <;iemand f'or*-. the

• report.

. He -,,said that )i *.symposium was* recently held, to discuss,. *: *.\\. -

further matters. relating.. to high--:tevel wast~

• disposal, and that EPRI indic*ated that it would.'like to_ c.ontinue the -discusi:;ion '

• . further. Also, DOE. has r~cently issued *a draft report based *on* its

.. re~iew of the. report on "Rethinking High-:-Level Radioactive Waste

. Disposal." *

• .In +esponse t~ a: questi,eh. by b~. Sh.e\\vmo'n _ab.out Congressional *r~view *.

of. this matter, _Dr. Parker stated:* that* Congress has no intention bf ;reviewing_ this matter.unl~ss _they are ab_solutely farced._ to... :. * *

.~

. -~.

Th_fs'_was,*an,.~~f*o~ati~n briefing **and*~:the--c~~ittek dld rio.t tak'e any *

a~t~on on this* ma~ter

~.;

• .~..

'i

v.

1 certification of *standardized Plant Designs.

• I...

tN<Yr.E:

Dr.*. M:.

Ei-zefta'.~ *was the Designated f~deral Official fqr.... *

• this ~o;r,tion. of the*'~e~ting.]

Mr:. : Wylle, *.Chairman, of the Improved

~ight

• Water

• React~r~

(..

~

.,Subcommittee, stated.that the. su_bcommi ttee me*t. with the

• NRC. staff".. **

• and' NUMA.RC represent.a ti ve$ on D.ec.ember** 4,. *1990; and. *disctjssed *.the' -.,,_.*

Staff IS. latest:* proposal regarding: -the level. 'of

• design: detail required for cert if icati.on under 10. CFR.Part 52.. '..

• ~.

NRR P~~sen~ation': _: Mr.. M. Virgilio/Mr.' E.. -I~b~o~, N~ *-

Mr..

Virgilio,.* ~RR, -- 'itl_cii6ate_d.that on August

• 2i,., 1990,". the * **

• Commission requested a. paper, froin the staff:. qescribing the.*.

advantages.. arid disadvantages of the two-tier *approach *that.is proposed* by NUMARC.

The_ Commission 'requested.also the staff i 5; recommendations on. those.* structures,. systems, and *components. for, which it may not be feasible or practical to achieve a level*.* of

• desi~n detail *iri the applicati6n consistent.with level~ i and~

Accordingly,* the staff i~sued SECY-~0-377, "Requirements for Design certification Under 10 CFR Part 52," on November 8, 199.0..

• In SECY-90..:.377, the staff states that. :t,he. information developed. by an applicant for design* certification shall be considered to be i~ one of th~ee categories£.

i 368th ACRS Meeting Minutes 11

'. ~.

Design material submitted* in an application and certified through rulemaklng (Tier 1) will include information completed during the conceptual phase of *the design such as design.*

criteria and bases, and certain information developed during the*prelimiriary.and detailed design phases~

Tier 1 can. be changed by a rulemaking to. amend the certification, an exemption pursuant to 10._CFR 52. 63, "Finality of Standard*

Design Certifications,*" or a rule waiver. pursuant to 10 CFR 2 ~ 758, "Consideration of Commission **Rules and Regulations in

• Adjudicatory P.roceedings. 11

. ** Changes rel?Ul ting from a.

-rulemaking become. binqing on all licensees refere~cing the.*

• certified design._,.

\\~~.

The remaining design information in *the application and not certified (Tier 2) will include.information demonstrating how Tier 1 criteria are implemented. and will be of sufficient '

detail for the staff to. perform... its safety review* of. the adequacy of Tier 1. The combined operating license (COL) will

.. be.conditioned f:!UCh that the -'COL" holder. may make* changes to Tier' 2* *~esign information purs~ant to provisions****paral.Ieling*

that, of 10 CFR 50. 59 I "Changes, Tes.ts and Experiments I" until..

such time.as 10 CFR..50~59 becomes effective*~** Changes to Tier

.2 information may *be subject to hearing before,the NRC. grants**.. '

permission to operate depending, "on

~nether compl:.-iance with *..

acceptance cri:teria is implicated by the chan~e.

Information developed. and available *for NRC audit may be:

_9h~nged provided the change does.not vl.olate the provisions*

of the application and certification.' *The staff will perform, audits. of *this design material to *ensure that the design products *meet the commitments of the design cer.tifica:t:~on and.

. supporting design details.'(Tiers 1

and

2) *.

If such information form:s the. basis for.. the staff's. formal safety

• determination regarding.th~ adequacy of Tier 1, it wiil :be* *** *.

docketeq as part of the.application. *

~r. -Yirg.ilio stateq. that. the staff is currently recommending t9 develop and issue a regulatory*guide that.describes for applicants..

the contents of an*appl1cation for*desigri certification and COL,*

the design *products expected to be developed and available.*for

• audit, and the process for. makincj changes* to the design.

In addition, this regulatory guide will provide guidance and.. the formulation of an *inspection, tests,* analyses, and acceptance

.criteria (ITAAC) program.

Mr.*. Imbro, NRR, outlined the staff~ s *proposal as provided in SECY-90-:377.

He said that the staff is proposing to use a graded approach to determine design detail to be developed by ari applicant.

The level of detail will *vary from system to system

\\

368th ACRS. Meeting Minutes 12 based on safety '(including the a.dditional. safety benefits from*

standardj,.zation) and will r!=cog~ize the limits set by what.* is feasible and *.practical.

The** applicant will submit in the application a depth of detail similar to.* that. *in an FSAR at the operating license (O~): stage for a*recently (1985-i990) licensed plant except for site-specific and*. as-built information.

The applicant* will develop and retain for staff audit *additional design infor,matio11. such as that normally c.ontained in certain procurement specifications and: construction *and installati~n spe,cif ipations..

• ,:*The staff analyzed.. the. feasibill.ty.. of. completing the. design

.. proc~ss.

From this:* analysis I

,- the : st;:.aff determlned that the feasibility varies with~

1the system grouping*'as follows:

Nuclear.island (p~imary system/co~tainment) - finai design in pr~cess (greater than, levet 2).

Balance of, nuclear.island and turbine island -

.det~.iled design complete (level 2) * *

• • ~

~.**

Site-specific systems, structures, and components - conceptual-

• .design and design interfaces complete *{Level 4-).

~

• Mr. Inihro cited _examples of.* ~*Tier::*-1 11 *"info~ni~ti~n* ~uch *as:;.*

~

}.~

e

. Pesign bases and_ criter.ia.

Simplified* piping and.instrumentation.diagran\\s.

• . :*. Simplified electrical ~ingle-:iine. diagrams class

.. General* arrangement drawings.

.1~ AC/DQ~

Loca~ion of equipment.

Rout'ing *of all piping~ : *

• • Routing of. cable tray systems..

Tier* *i information would be that. contained in the standard 'safet:y_

• "Analysis Report' (SSAR)

~s required* by "the scope _of the SRP and standard format and contents document but not specified. *as Tier 1..

'f, l*

Mr.'. Michelson commented* that in SECY-90...:377_.the *st:~ff proposes to

• . 'treat* Tier 1 and Tier 2 information in a similar fashion up to the

• COL issuance. *He. stated that the staff *should allow ;*a process "

similar to that. o*f 10 CFR 50. 59 for making changes. in Tier 2

. *beginning after design certification.

.Mr.* Wy1ie agreed with Mr.

Michelson. '. *

• Mr. Michelson cautioned *that hazard analyse*s (e.g., fire,. flooding,

.and pipe* breaks outside containment).* should be loolced at very carefully.

He pointed out that the staff. c:ioes not have* clear crit~ria to revie~ such~items.

Mr..f.iichelson stated that essential service water '(ESW) system and non-ESW systems are identified by.the staff as site-specific requi!ing a Level 4 design detail.. However! ~pose portions of the

e.

368th ACRS Meeting Minutes 13 ESW and non-ESW systems located within the n~clear island or the turbine island need to be detailed and considered in th~ staff'~

safety determinations. Mr. Wylie an~ Mr. Carroll agreed and.shared the same sentiment.-

Mr._ Imbro st~ted that approximately -one~J:ialf of* the engineering hours expended in design during design and.:construction of a*

nuclear power plant are expend~d in the final desi9n. and field engineering phase.

Mr-. Ward-expressed concern* in regard-to the. information __._provided.

by the staff for the design finality issue and the expenditure of engineering hours. He indicated that such information is hot based

on real experience _or hard data from the* industry.

The sta:ff

• agreed.

. NUMARC Presentation - Mr. *W.

• Rasin, NuMARC.

- Mr~ -Ras in_, NdMARc, presented the industry's general *comments - on.

SECY_;90-377. *. -

• He _ stated th~t the industry. recognizes. and appreciates the.- effort the* staff has made in drafting-SECY-90-377. _

However, the industry - has general concerns _ in regard

• to the:

following:

In SECY-90::-377, _.tne

~taff. recommends_- new and substantial requireme11ts beyond *10_ CfR Part. 52-~...,

The finality statements as -reCOIIIIIleilded by.. the* staff are ambiguous and could lead to an unpredictable licensing process*

and schedule.

The "feasible and practical" standard that 'is introduced *iri the level of detail is not clear and does -not demonstrate safety benefits. : ~

~

There,is no need to develop a regulatory guide on level of detail, s*ince the current, regulat_ions are suffi¢ient.

I~

There *will be-_ additional* cos_t~ to meet the leve).., of.._ detail required by SECY-90-377 -- the*.industry_ estimates being* in

'excess of- $500 million for :four* ALWR projects. -

- The implementation *of -the provisions of SECY-9o'-377 -will cause schedule extensions -- approximately_three to five years for evolutionary plants --and t;his will also.impact passive plant designs.

Mr. Rasin recommended that the Commission not approve SECY-90-377 as written; he stated that if SECY-90-377 is e_ndorsed, the Nuclear Power Oversight-Committee (NPOC) strategic plan and nuclear option

368th ACRS Meeting Minutes 14 will be jeopardized.. The industry is pl~nning to-provide detailed comments on SECY-90-377 to the NRC staff and the Commission as so9n

• ~s possible.

Mr. Michelson commented that* the*- -ACRS would expect the levei of

.. information for staff review to include that required *to specify the environmental qualification requirements for. all components that are important to safety, -including those outside the primary containment.

He added that 'it is not clear** if SECY-90-377 has provided the level of detail for all events that are identified in.

the SRP for ma~datory analysis. *

. If no;t, the issue of how. to specify the env'ironmental qualification requirements. for* those components that assure reactor shutdown and suitable mi tigat1an*

• during such events appears to be~unresolved.

• Mr. Carroll expressed *concern that the staff is still.. using. -the RESAR-414 acceptance criteria for* the Integrated P~otection System*

"previou~ly evaluated by the staff 11 years ago.

The staff agreed.

• Fo~lowing further deliberations, the Committee* provided a report

. ori SECY-90~377 to**the Commission as discussed in :Section IX of this:

document.

~ -

~ '

VI.

Nuclear Piant *Operating' Experience and Events * * *

- [NOTE:

Mr. *"P. Boehnert was the Designated* Federal Officiat for

~his portipn of the meeting~ ]

Mr.

Carroll,* ch.airman. of *the.Plant Operations* subcommittee, introduced this topic to the Co~ittee.

'\\. *""

• NRR*Presentation

• overview -

Mr *. A.* Chaffee, 'NRR

~I Mr*

Chaffee

~tated-. that the **staff w.j.11. brief the Cominit,tee*

regarding the following,operating events_::

Sequoyah:*,Units 1 & 2 -

Hydr~gen Gas Buildup in Chargin*g

. System;.August 22, 1990. **

• Bruns~ick, Unit 2 -*Main Isolation Valve. (MSIV) Closure at Full Power, August 19, 1990.

Brunswick, Unit*2 - Loss of Offsite Power, June*11, 1989.

Pilgrim -

Feedwater System Malfunction and Reactor Core

~--Isolation cooling (RCIC)

Syste~ Failure, *September

. _2 I 1990 o

e e

368th ACRS Meeting Minutes 15 Hydrogen Gas Buildup in Charging svstem at Sequoyah units 1 & 2 -

Mr. l'.f. Caruso/Mr. D. Fischer, NRR..

Mr*. * <;aruso, NRR~* stated. that the issue of gas buildup in_ PWR

. charging systems. i's generic.

The principal concern is the potential for damage or destruction of the.high~pressure ECCS pumps on demand.

In response to questions *from Dr. Kerr, NRR repre*sentatives stated that several Information Notices have been issued.on this concern,*-

• and. another ~ddressing the subject.event will be issued 011 December

. 10.*, 1990.

Mr*. Rossi said that solutions are available for this:

is~ue; it is really a. question of getting the job done.

~..

. Mr. Fischei;-, NRR, detailed the specifics of the event at. Sequoyah.

• On August 22," 1990, during technicai specification surveillance.of

• a ('.barging plill\\P on Unit 2, gas was discovered both in the charging

• systein piping (-10 ft3 ) and the crossover piping (-5 ft3 )- to the.

r Residual Heat Re~ovai '(RHR) system:

• The gas was. identified as being hydrogen.

• The cause of* the buildup was *attributed tp_ :gas

. stripping bY.*the mini-flow orifices.. A nearly idel')tical event

• occurred on Septem~er.9, 1990 at Sequoyah,* *unit 1.

~~- Carroll asked for the basis that Westinghouse used for* stating*

to the licensee that continued oper~tion wai;;*acceptable, provi.ded

• gas accumulation di.d not exceed 6 ft.

Representatives of. NRR said

. that th~y are not.sure of Westinghouse's basis* for.this statement..

. In response to a ~estion from Dr. Kerr I the NRR. staff said that'.

• to date, no* pump has been* damaged*;* however, -the potential. for darilag.e is real..

Dr. Wilkins asked:.if the problem is detectable.. The NRR staff said that it could be detected :via fl_o'Wmeters and/or by use of ammeters (if the pumps are.so equipped with the latter).

Mr~ Chaffee noted that NRR.doesn't kno~ why the gas is coming out of solution.

Therefore, the staff's focus has been on prevention*

of pump inoperabl.lity so as to precl.ude the common....:mode failure:*

~

The staff stated that_ the licensee (TVA) was cited for a Level IV vio.lation due to their inadequate corrective action for this issue.*

Both the statf and. INPO had repeatedly called attention to this concern in the past. _

Mr.

S.* Mitsky1 Science Applications-International Corporation (SAIC), discussed the result~ of a technical evaluation of the operability of a PWR ECCS. centrifugal charging pump,. assuming the

-ii,

• 368th ACRS Meeting Minutes 16 presence of hydrogen gas in the crossover piping.

SAIC was contracted by NRR to perform this analysis.

The analysis was for a specific Westinghouse 3-loop PWR pump/piping configuration.

Results-of the study show that.the pump will fail in a matter of seconds after the gas (in a high void state) enters the pump.

Mr.

Mirsky said that this result is both plant and sequence specific.

In response to.Committee que~tions,

• Mr. Mirsky said the key parameter impacting punip performance is the void fraction.

Be'low

-5% void,* the pump should be operable; performance degrades significantly when the void is >20%.

Also crucial, is the extent of gas/water mixing*tha:t occurs.before the*void enters *the pump.

In.response to Mr.* Carroll, Mr~ Rossi stated that Westinghouse has seen the SAIC analysis and is* in substantial agreement with. the

results.

Mr. Caruso said that NRR has a Generic Letter under* preparation that requests the affected licensees to evaluate*.their piping systems to determine the. extent of the *problem arid. implement

. *corrective actions, as appropriate.

In response to a question from Ml:-*. Michelson, the staff stated that it has.not looked** at BWRs for this problem, but wi11* do so as part of the ge:r:iericcommunication p~ocess.

MSIV Closure at Full Power at Brunswick unit 2 -*Mr. G. Belisle, Region II Mr. Belisle, NRC-Reg.II, who led the Augmented Investigation. Team..

. (AIT) for this event, provided *details of the MSIV-closure incident.

While at 100% power/ one technician (although two t~chnicians are required) was testing* *the primary containment isolation system..

• The* technician tripped a *channel prior to*

resetting 'another, which resulted in closure of the MS IVs and

. subsequent reactor trip.. The.missing technician, who was supposed*

to be providing independent verification of. the *first technician's. :*

efforts,: provided false verification of his work.

Following scram, several valves. exhibited degraded performance~

Five safety relief valves (SRVs) failed to open. on demand; the

• RCIC throttle valve failed on thermal overload after repeated cycling.::

The AJ;:'!'.. concluded that the event was caused* by intentional departure from step-by-step procedural compliance/verification, exa?erbated by lack of command and control by operations personnel.

Corrective actions taken included:

• ~ \\ *.

368th ACRS Me~ting Minutes 17 Firing.of the technicians involved.

Initiation of formalized communications training.

• .. Adoption.of* standards of excellenqe by maintenance perso'nnel..

Upgrading of procedures and remode*ling of the simulator to

• enhance the training of the operators vis-a-vis operation of*

the RCIC and throttle valves!

• Loss of Offsite Power at Brunswick.<<. Unit 2

~ Mr *. R. Karsch, NRR Mr. Karsch, NRR, reviewed* the June. ;1.7, 1989 loss of off.:__site power (LOOP) event at Brunswic;:k, Unit 2. *The event began with Unit 2 at.

100% power.

A ground *fault alarm for the start-up transformer (SUP) was.received fn the control room.

A relay crew was sent:to trouble shoot the $UP.

The plant manager (called at home).advised the operators to reduce. power 'in case there was a SUP lockout.

The.

manager intended that the* operators drive rods in to reduce *powe~ *:

so :that the pptential for power instabillty'/coreoscillations was*

minimized if recirculation pumps (RPs), powered fr.om the SUP,.were

~1ost due to a SUP lockout.

The operators reduced power by fl.ow.*

reduction of the RPs, not understanding the r~a~on for-the powei;- :*;.

cutback.

Due* *ta *improper trouble and* the RPs tripped.

prevention of possible tripped manually *. This from. the. SUP.

shc;;oting procedures,. the SUP d:j.d lock-out Pursuant to the* NRC Bulletin 88-07. en-core power instabilities, t:he reactor was' re~;ulted in a LOOP, due *to powe~ing the RPs In response*to:a*question from Mr. Ca:r:roll, Mr. Karscl) said th~

licensee could have. powered the RPs from *the unit *auxiliary

. transformer,* which would have *prevented a LOOP upon reactor 'trip....

The SUP was used.because of a desire to prevent a trip of tl)e RPs given a reactor t_rip.

(A *trip of the RPs* usually re.sults in loss.

of th,e,seals).*

A nine-hour~LOOP ensued; the emergency diesel generators operated satisfactorily.

In response to a comment. from Mr. Carroll, Mr.*

Karsch s:tated that it takes -

7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to disconnect. manually the maingenerator.. from. the iso-phase bus in' order to restore on""-site power.

A cross-tie from the Unit 1. switchyard was *available, if*

needed.

Mr. Karsch rioted that the:re were three separate human er*r*ors.

committed that contributed to this event.

Dr. Kerr *said this event demonstrates the need to make plant

• systems fault-tolerant.

He asked if theNRC is investigating the safety implications.associated with the conduct of special or unusual plant t.ests.

Mr. Karsch said that both the NRC and INPO are looking into this issue.

l'

368th ACRS Meeting Minutes 18 Feedwater System Malfunction and RCIC system Failure at* Pilgrim -

Mr. R. Karsch, NRR Mr. Karsch, NRR,.stated that on September 2,**i990, *feedwater contrc;>l was lost and the plant was tripped manually.:

Component fail,.ure in.the feedwat;er. 's'ystem with contribution. froni maintenance oversights and a defective proce_dure'combined_ to cau::;e this event.

. Following plant trip/*the operators *attemptec;I to start manually: the RCIC fa,r vessel feed;.due:to a flaw inthe procedures, the RCIC turbin_e tripped on overspeed.

TWO additional restart.0attempts :were unsuccessful, as *a result of damage caused bY the overspeed** trip assembly and prior-p~or maintenance.

Upon loss -of RCIC, an attempt was made to feed the vessel with the

.. start-up feed system.. The feed regulating valve failed.at the

.fully open position.. Vessel: feeq_ was. maintained by.~cycling the.

ma'in* *feed.pumps *and directing: the flow through the failed ppen

. valve. :. Later, level.was. controlled. by using other pumps of' tower.

capacity.

_Subsequent to the event, :i,t was disccrifered that. the RCIC. suction piping. *had been -overpressµrized and that. the train'* of the-. *RHR system used for.shutdown cooling experience? a mild water hammer event.

• Mr. J. MacD.onald,:: Region I, stated that the operators h~ndled; the event very well~

• Mr~* Carroll asked for a "progress report",'. on Pilgr~m, since restart.

• Mr.

MacDonald.. '* indicated that.' the

.l_icensee' s performance is continuing to improve.

Perturbations' 'in operation :,resulting from past problems still. puzzle* them**a bit, but the. licensee.' s 'everit analysi.s. an<i di~gnostic skills* are very good.. *

~"' \\

Mr*. Carroll. reques:t~d that the staff Keep the Committee. informed of its ac_tions* concerning resolution of the gas binding issue. *..

Mr~ Carroll -thanked. tl:le personnel from. the Regional Off ices for"

.*attending. the meeting' and' the staff. for' an excelleht set of

• - presentations:

VII~

Development of New Standard Technical Specificatioris *

[NOTE:

Mr. P.

~oehnert was the Designated Federal Of~icial for

-this portion of the meeting. ]

Mr.* Carrol*i, Chairman of the Plant Operations Subcommittee, int!oduced the topic of the NRC staff's efforts t6 develop new standard technical specifications (STS).

e.

36at*h ACRS Meeting Minutes 19 NRR Presentation -.Mr. Reinhart, NRR Mr.* Reinhart, NRR, reviewed briefly* the chronology of the STS program.

He stated that this effort began formally in February 1987, with the issuance of*an Inte~im Policy statement that laid

• *out. the ground rules for development of new STS.

• The staff expects to issue the "final. draft" of.. the STS in J"anuary 1991.**

These documents will be available* for review by.the respective owners Groups (OG).

• Following ~c review of the OG comments and* the*

lessons learned from implementation of the newSTS at lead plants,*

• .. the final draft of the STS and accompanying bases will be.. **ii;;sued

.. in the spring. of 1991.

Mr. Reinhart "stated that,. aside from NRC and its contractors,. there has** been. ~xtens.ive*' participation in. this,program... This includes representatives of *industry {NUMARC, OGs, lead plant, licensees,.

etc. ).

The leaq. plant_s involved include:

North.Anna, Units 1* and 2. (Westinghouse) crystal River,. unit 3..

• • (Babcock and wi1c*ox).

• San Onofre, Units 2 a_ild 3.. (Combustion Engineering).

Hatch, Unit 2 (General Electric, BWR-4)

• "Grand Gulf,* unit"'i *

(General Ele.ctric,

• BWR-6).

Mr..

Reinh~rt h~ghlighted *the changes made in th~. new.. STS.

Reg~rding technical changes,*_.,... 40% of the current requirem~nts -have*

be.en. movep from the technical specific.ations (TS) *to other: licensee controlled documents..

• f1r ~ Michelson asked if NRR checked to ensure that significant problems would. still be captured given the'above

change.

Mr *. Rossi said the *staff has not conducted a thorough

• r~view to ehsure this is* the case, but indicated that* they would*

look* into *this.

~..

Mr. Reinhart* stated that NRR.used risk. insights as ari aid.to the

. developme;nt of this program.

Risk. insights were used to. help

• • det-~rmine what requirements should be captured -in the new STS.

• In

addition, SAIC. per'formed *an evaluation to determine the rii;;k

• significance* of TS changes.

In response to questions from Dr.

Kerr,.the staff* said that SAIC evaluated the "delta" to the core*

melt frequency resulting from r,evision/deletion of TS, using data from the.NUREG-1150 plant studies.

The goal-was to ensure that

.plant risk was not impacted deleteriously by these changes.

Mr. Reinhart stated that the new STs* have. a tabular format with concise statements of what an operator is to do and how much time is.available for.. the action.

He noted that copies of the new STS will pe provided to the Committee for its information~ *

,~-.

368th ACRS Me~ting Minutes 20 Dr. K~rr asked :whether the staff has d~termined ff the new STS *will enhance plant saf~ty. *The staff stated that it has not analyzed

. this question on a quanti tati ye _basis.

Qualitatively, the staff

• believes that safety will be enhanced because the operators.will be freer to focu~ more.6f their efforts on the actual.operation of tty:? plant.

In response to Mr. Carroll, th~ staff stated that 40% of_ the limited'* *condit"ions for operations (LCOs) in the current TS were.

deleted *in tQ.e new ST_S.

• The new STS were exe~cised ori a simulator

• at.the NRC Training. Center* in Chattanooga; the instructors (former Senior Reactor Operators) gave favorable **comment on tl)eir µse.

• Mr. Michelson asked liow the acceptance criteria. for. a*.'. given requirement that was moved out. *Of.the TS document gets* changed.

Mr*. Calvo stated.'. that such changes wil'l be controlled under the 10

• CFR 50. 59 review* process.

Comments by NUMARC -. ~

,* w *. Hall,. NUMARC

-t" Mr. Hali, NuMARC,.stated that NUMARC-*ha:s not. had* -cfiscussion w_ith the' sta~f.on _the new.~TS since August 1990 ~*. As such, NUl-IARC is.

reserving comment on \\the content of the current.documents.

• NUMARc;:

exp~cts to* review the new STS-upon release and* hold meetings with*

the NRC

• staff.

Ap appeal *

• process is availabl~

• f ot... any disagreements that cannot be *resolved at *the working :

• 1evel *. *.

• Implementation on* the lead plants. will not 'begin until. the new STS.

are in final form.

• In response to a* question from Dr. Wilkins concerning t:tie remairifpg pr_ogram

• schedule, Mr. *Rossi stated -that the staff. hopes to issue the *fina*l version *of *the STS in the spri.:ng of 199i *following receipt of industry comments, as well as ACRS comments. Responding to further qu~stions,: it;. was noted.that the*STS issued by NRC will still. have to be_ converted to a plant-specific set of.*Ts.

The

~ntire conversion.process will take about. three years for a given plant to complete'.

Mr. Michelson *asked'* if NRR -has *reviewed the NSAC-125 document, "Guidelines for 10 CFR 50*. 54 Safety Evaluations," dealing with the 50.. 59 review proce~s.

Mr. Rossi said NRC reviewed NSAC-125 and provided comments to NUMARC.

NUMARC, in. turn*, issued the document".

incorporating NRC's comments.and solicited industry comment on its use.

NRR intends to review the document again prior to its adoption by. the agency.. Mr. Michelson suggested that the Committee review NSAC...,125; Mr. Carroll stated that the Plant Operations Subco~ittee would hold a meeting to review the use of NSAC-125 when review appears timely.

368th ACRS Meeting Minutes 21 Mr..

~arroll "indicated that th~.Plant Operations Subcommittee will track the progress of the.new STS development program. and hold a meeting. with. NRC and. industry p:r-ior to issuance of the final version. of the new STS.

Subsequent. to this~ **meeting, * 'the Subcommittee will recommend a course of action for the' full

• *cominittee for.consideration.

VIII.

NRC Safety Research Program

[NOTE:, Mr,* D. Hm~ston was the Designated Federal Official -for.this,

• ":portion of the meeting. ]

Dr. Catt<;>n, Chairman_of the Safety :Research Program Subcommittee, said that about ()~e -and one-half years ago Dr. N. Zube*r,.. RES.,* was asked to address 'the scaling issue assoqia:ted with severe acc'ident

• experiments. The direct containment he~tirig (DCH) issue* was_,:chosen for an* ::initial application.*

• The. project is n*ea:rly compl_eted _and a draft'. report is e)cpected soon.

He said that Dr. -. zu_ber would be retiri:r:ig at the.: end of Dece.mber

• 1990.

"<:severe Accident scalin~ Meth~doloCJv:.:. Dr. N. z.uber,.. RES. *,*' *..

I

~

1

~

~ :

Dr. *-Zuber, RES, discussed the Severe Accident Scaling Metbod.olo_gy,.

(SAS.M) in regard to its develop111ent and intended applicatJon.

His presentation addressedthe following* topics:*

.\\'::

o:verview of integrated structure for technic.al

resolution (ISTIR).

• Brief description of I STIR components.... *

• overvi~w.qf. SASM~

• Brief description of SASM components~

overview of.the two_;tier'scaling analysis *.

• Application to DCH transients *. * '

Content of report.

issue Dr. Zuber noted. that SASM had -be~n developed by a Technical :Program :

Group (TPG) made up of 16 experts frpm. industry/ academia, a:nd *

• national labor~toi:;-'ief?.

The TPG has held.'nine meetings to. date.

A draft*of its final report is anticipated to.pe completed.by.t)l.e:

mid~le-,of January 1991. The principal objective of this effort was

'to provide a scaling methodology that:.. wou],.d' 'be systematic.'*and* '

practical I audi table and traceable~

This would. ensure.. -the..

prototypicality of

• experimental data.

A two7tier scaling methodology, one based on the system approved (top-down) and the

, other on a process approved (bottom-up), was developed and applied to the OCH process..

Dr.

Zuber concluded that. SASM met the predetermined objectives _and should provide.the capab~lity. to* scale up processes to conditions relevant to nuclear power plant operations.

36Sth ACRS Meeting Minutes.

22 Use of SASM Sheron, RES in the severe Accident Research Program -

Dr.

' ~ *-

~

B.

Dr. Sheron, RES, discussed the use of SASM in the Severe Accident Researqh *Program (SARP) and the role of SASM in the re~olution of*

.severe accident issues.

He stated that while.SASM was developed to. address scaling faqtors for, the. Sandia National Laboratories

. ( SNL). Surtsey OCH tests, SNL is. responsible for all facets of Surtsey and.has chosen to form its own scaling group to review the tests.

+n addition to the integral tests,.some separate eff~cts tests are. planned to contribute to the scaling ~valu~tions.

In

• regard to is.sue resplution, Dr. Sheron stated that experiments are only one facet of the complex OCH* issue.

Other facets i,pclude

.accident management. schemes a:Qd*' the 'likelihood/risks associated with containment failure by* J?CH. *

"In respqnse to a question.. by Dr. Kerr r~garding a deter~inatfon. ~f the.-adequacy of scaling, Dr. Sheron and Di;-. Zuber briefly discussed,~

.. the *test programs to be per:eormed in Surtsey (1/10 scale) and at ANL -(1/30 scale)~.

• D_r.- Catton questioned whether DCH. was a probl~m*. when the.core melt

, r

. fraction. was be*low *4o%..

Dr. Sheron stated that -the DCH prob:i,ell_l appeared to _go C:lW~Y. at;. this point but that this matt"er. ~s s:till. :

• under r~view.

In response to questions by Dr.'**Kerr and Mr;.carroll,,, Dr*~* Sheron discussed the positive and necj'ative* attribut.es *associated *with.

inadvertent and.advertent vessel depressurizat~on.

He noted also how this is currently addressed in some. emergency.* operating pro_cedures ( EOPs).

In response to a question* by Dr. catton, *Dr. Sheron *"stated that.

RES would like to assemble a group of experts to address in-vessel core mel:t: progression.

This group would provide guidance for the development of the,MELCOR. code.

Also,* in regard to scaling for natural** circulation tests, Mr.

Wright, RES.,

noted a scaling analysis by. Westinghouse and offered to provide a copy* of.the related. Westinghouse report to* Dr. Catton.

368th ACRS Meeting Minutes 23 0

~X. Executive Session A.

Reports to the commission SECY-90-377, "Requirements for Design Certification Under

• • 10 CFR Part 52" (Report to Chairman Carr, dated December 10, 1990)

The Committee commend~d the staff.for its accomplishment in producing SECY-90-377 on a complex subject*and in a relatively short time.

The Committee provided several

• comments and recommendations, including the* following:

. Al though the Committee concurred with the staff Is graded. approach for defining the level of design required and the proposed tiered approach, it did not agree t:hat the vast amount of information and.

level of detail. proposed to. be included with the.

application are.needed for,a safety*determination.

Therefore, the Cpmmittee recommended*-that SECY 377 *not be. issued as presently written.

., Tier 1 and Tier 2 information should b~ *limited to that *.required for the staff's safety

• determina~*

-tions.

• The same process proposed in SECY-90-J77 for making,

• changes to Tier 2 information for the period between

. ~omb'iried operating license issuance and operation should be permitted for* making. ch_anges * *tor the per_iod beginning after design certifica~ion.

I.

The Conimission should instruct the staff to proceed with the preparation of the. regulatory guide.related.

• to level of

• design detail.

The focus of the regulatory guide should be - on that int"ormation required for the staff's safety determination.

• The Commission should instruct the staff to update the Standard *Review Plan so that it *can support

• design certification. reviews.

• Full:--Term Operating License for the Dresden.Nuclear Power Station, Unit 2 (Report to Chairman Carr, dated Oecember 11,* 1990)

The Committee stated that the procedures* and schedules that }1ave been agreed to by the *staff and the licensee for the resolution of the remaining three Systematic Evaluation Program (SEP) issues and of the Unresolved

368th ACRS. Meeting Minutes 24 Safety Issues (USis) and TMI Action Plan items are satisfactory, and that the remaining actions to resolve these items would not be accelerated by withholding a full-term operating license (FTOL).

The Committee expressed its belie'f that there is reasonable assurance that the Dresden Nuclear *Power Station, Unit 2 can.,continue to be operated at power levels up to 2527 MWf under an FTOL without undue risk to the health and safety of the*public~

Full-Term Operating License for the Palisades Nuclear Plant (Report to Chairman Carr, dated December 11, 1990)

The Committee stated that the procedures and schedules that have been mutually agreed upon by the* staff and the licensee for the resolution of the remaining three SEP

• issues as well as. the* US Is and TMI Action Plan items are :

satisfactory, and that the remaining actions to resolve these items, would not be accelerated by withholding an FTOL at this time.

The Committee : expressed its belief that there is reasonable assurance that the Paiisades Nuclear Plant can continue to be operated at power leveis up to 253:0 MWt under an *FTOL without undue risk to the health and safety of the.public.

Westinghouse's Application for Preliminary Des ion Approval for the RESAR SP/90 Design (Report to Chairman Carr, dated December 12, 1990)

The ~ommittee provided several comments and recomm~nda tions on the 'staff's Safety Evaluation Report'. * (SER) related to the SP/90 standard plant design, associated Preliminary Design Approval (PDA) document, and on the SPj90 design features.

• The Committee expressed its belief that, subject to.the comments* noted in its report to the Commission,. the

'proposed design of the RESAR SP/90 Nuclear Power Block (NPB) can be. successfully completed

• and used in an application for an individual plant construction.permit.

The Committee recommended that a PDA be issued *for the

• proposed Westinghouse RESAR SP/90 NPB.

The Committee commended Westinghouse, the Japanese APWR program participants, the EPRI ALWR Utility steering Committee, and the EPRI staff for the effort they have expended in the development of.the RESAR SP/90. design.

368th ACRS Meeting' Minutes 25

a.

Memoranda Press Announcement -*ACRS Vacancy (Memorandum for. John Kopeck, *office of Governmental and Public Affairs, from

• Mabel F.*Le~,, AC::RS, dated December 11,. 1990)

The Committee agreed tp revise the proposed Press. Release to add th$ foliowing s*entence :PFoposed by Chairman Carr:

. "At this. time, the Commission is. *especially.

• . interested in. members

• who

. have direct experience in construction, operation, and

• \\

testing of ~ucl~ar~power plants~fl Consistent with the Committee's. d,ecisiori, Mrs.. Lee transmitted a revised*'~ress Release to the Office *of Governmental. and. Publ~c. A,ffairs

• for publication in the news '.media as well as *in. selected scient:j.fic and en-gin~erin~ magazines~

Prescheduled ACRS-Meeting~.. w'i th *the **commissioners (Memorandum for Saniuel*J. Chilk, Secretary *of the Com-missic::m,

• from R.,. F. Fraley, ACRS, dated December 14,* *

. " 1990)

Mr. Fraley has. informe.d ~r. Chilk that the Committe.e members have ~gr~ed to the fpllowing dates for pres.,,._

chedulecf ACRS meetings with the Commissioners during,.CY 1991 :*

ACRS Meeting

. 37.0th 374th 378th

• Dates

• February_ 7. or 8, 1991 June 6 or~7, 1991 October 10 or 11, 1991

- *,1*

Mr.

.* Fraley requested that. SECY confirm that these proposed d,ates. are. ac~eptable to* the *Commissioners.

c.

.subcommittee Report Adopted.Plants Activity Dr. Lewis :r:eported briefly on his successful. visit to San Onofre Nuclear Plant, Units 1, 2, and 3 on November 16; -1990.. He was accompanied by AC~S meIT1bers Dr. Catton and Mr.

Carroll.

The licensee briefed the members regardin9:

368th ACRS Meeting Minutes 26 operating history

.Major improvements Reliability centered maintenance Rerackihg of fuel poo_ls *.

Individual plant exa~ination program Repair of the Unit 1. th~rmal shield

-This was followed by a plant tour that included:

control* rooms of all units Diesel ge~erator room for Unit 1 Ttirbine deck and outside containment for Unit 1 The.rmography denionstr~tion *on *the. auxiliary f eeci- *

. water line for Unit 3.

o.

other Matters Election of ACRS Officers.for CY.1991 T.he.~ommittee members elected tlle following Officers fo;r CY l991:

. 1**

ACRS 'Chairman :

• - David.*A..ward ACRS Vice;_Chairman *. - Paul G. **shewmon Meriiber:-at-Large of t;.he Planning - *James c. Carroll

• an*d

• Pr9cedures Subcommittee International Activities ~ Meeting with Japanese Repres~

• entatives -

(Hitachi, Toshiba, Tokyo Electric, MITT!,

. and Japanese Advisory Cammi tte*e)

The Committee decided to send a subgroup of the commit- *.

. '. tee to meet w,ith'. Japanese representatives to concentrate.. :..

• on issues related to ABWRs *. ' This meeting is tentative~

"iy scheduled. to be heHi in c*Japan quring the end.*of *cy

_. 1991 or early.. part of *cy 1992..

or*. Catton suggested;;

"that this meeting.be coordinated with the SMIRT *confer-

. ence scheduled to be held in.Japan during August.1991.

.,E..

summary/List of Follow-up Matters

• I.f the* industry is ready and willing, the. committee

• agreed to hear another briefing. by the industry..

• representatives during *the January

• 10-12, 1991

• ACRS meeting regarding their". concerns/ comments on the

• proposed staff

• position9. cont;.ained

• in SECY-90-377, "Requirements for Design Certif icati9n Under 10 CFR Part 52."

• This matter **has been scheduled for the January 1991 ACRS meeting.

NOTE:

This item has been deferred.

(Dr*. El-Zeftawy

• ha*s the follow-up action on this mat-ter.)

368th ACRS Meeting.Minutes

27.

r. *,;-

' '. ~,.

~'. \\.

The 'committee agreed to Jl\\eet with. Mr. Beckj ord_,. RES

'.oirecto~,' during the Jam.~ary 10"'."'12, *1991 ACRS meeting to

.discuss several matters including!

~,.

.. Impact, of the 'FY 1991.budget redµction of $'2.1 million on the NRC r_esearch program.

• r~pact. of *the anticipat~d OMB redu9tion to the FY 1992 ~b'l~.dget on. the NRC r~search progr_am.

Other *,items of mutual 'interest~.

. (~. Boe~:mez::t has _the. f ollow-:up.action on. this matter. ) **

The.*co~itte~ *agr~ed *with the p~'oposal *by or.

c~tton:;

• .Chairman* of the. Thermal. *Hydraulic Phenomena Subcommit-

tee,. to' *hold a Subcomm.i ttee. *meeting

• to

• discuss with representatives of-RES the adequacy of their responses to. the

• ACRS. comments and recommendations. contained in

• .. its ()¢tober 1i,* *1990 letter to th~- EDO on the docu~enta~

tie:>n *.of

• ttie NRC computer* codes..

(Mr.

Boehn~rt has the

. follow~up *action on *this matter.)

~

.:.1 The.Committee: agre~d with.. the p:r;oposal by Mr*. Carroll,.

. Chairman of. the Occupational/ and. Environmental Protec_-:.._..*

tion*;*systenis Subcommittee, *that p Subcommittee review of.*

the 'propo_s~d final version o'f l.o CFR. Part 20; *is not

.nepe~sary. and 'that the full* Commi.ttee. hear a* presenta-tion from the staff on this matter 'during.. the January 10-12,** 1991. ACRs* ~eeting... (Mr~ Igne:.--has*>t;he follow-up

.action.. on this matter. ).. '

... -~,-

.~

'J Th~*.coinmit tee

• agreed with a proposal ~y. Mr.. Carroil, Chairman *of the.* Occupa:tional

• and, Environmental -Prote_c:.:

.. tiori Systems *subcommittee, -ihat t:tier~.~s no. need for the-..

ACRS to* review* the proposed 10. CFR Pa.rt 36, "Licenses.

and

~adiation

• Safety Requirements for Large.. Irradi"'"

• ators~.'.'*

However,~** *.the

~ull Committee haf;;*- request'ed a brief_ing from... th.e*.. *staff. on

• this

• matter:. du~ing the January 10-12 I

. 1991 ACRS meeting..

(Mr. Igne 'has the

~ ~ollow-up *.action on this matter.)

The Committee reaffirmed its previous* position that a

• format. similar to that used for *_last year's report

• shou:J,d be used for the forthcoming annual ACRS report to the Congress** on the NRC* *safety Research Program and budget, and that.the transmittal letter *may be expanded

• to include*, -as necessary, ma)or comments and recommenda-tions..

Dr. : Catton, Chairman of the Safety Research

.e 368th ACRS Meeting Minutes 28

• Program Subcommittee,.* requested that. the ACRS staff provide him with copies of the ACRS reports/letters related to the NRC research program that were provided to. the Commission/EDO since the last ACRS report to Congress.

• Mr. Boehnert has transmitted the information to Dr. Catton on Dece~er 11, 1990.

(Mr. Duraiswamy and Mr. Boe;tinert* have the. follow-up action on this.inatter.. *)

. The Committee decided that -a proposed briefing *by the NRC staff-on the restart of Browns Ferry'* Unit 2, during.

the January 10-12., 1991 ACRS. meeting is not necessary

. '.since the ACRS Subcommittee on the TVA.Plant Licensing

• and *Restart Is scheduled to.hold a meeting on January 24, 1991 to discuss this matter.

This matter is also scheduled "for discussion* by the full Committee during, the.February 7~9, 1991 ACRS meeting.

(Mr:-

Hou.ston has the follow-up action on this matter.)

Mr *. W~rd, Chairman* of the Containment System~ *subcommit-tee, distributed the latest draft of-* the proposed report

. on Containment Design Criteria.*for Future Plants that was developed by the Joint Containment. Systems

• and Structural Engineering subcommittees.

He request~d

• comments from* :the members. on this. draft aric:i indicated t;hat **a Working Group of the Containment Systems Subcom-mittee is schedu:led to meet on January 9,.1991 to dis-cuss this *report* further and to* develop another dr'aft for submittal to the f-ull Committee for consideration during, the January 10-12, 1991:., ACRS :µieeting.

• (Mr.

Houston has the follow-up action on this matter.*).

with ;-egard* 'to a requirel1le.nt. in 'the November 6, 1990.

• $taff *Requirements* Mem*orandU:m

• related. to SECY-90-34 7 that The ACRS should review the survey results* and proposed corrective actions and provide CO'tllll\\ents.. to the*

Commiss:Lon, n the* Committee agreed _*with a* proposal by D.r.

. Lewis, Chairman of-the Regulatory Policies.and Practices.

Subcommittee,. that the ACRS review this matter after the public comments on the proposed cor.rective aC'tions have-..

.. been

• received and resolved.

The Committee instruct.ea.

• Mr. Fraley.to inform Mr. Chilk, SECY, of this decision..

NOTE:

• Mr.* Chilk >was informed. of *this decisicm.. on.

December 19, 1990.

(Mr. Fraley has the*follow-upaction on this matter. ),

D'r. Catton suggested that dµring the next ~.evere Acci-dents* Subcommittee meeting, arrangements be maqe for a briefing by the NRC staff. and(or Sandia** National Laboratories (SNL) -on the steam explosion*matter, p~r ticularly information gathered through. the steam

. )

.368th ACRS Meeting Minutes 29 F.

explosion experiments perfqrmed by SNL.

(Mr. Houston has the follow-up action on-this Il\\atter.)

_During the discussion of the reactor operating events-,

-the f ollowi;ng request and agreement were made.

{Mr. -*

Boehnert has the follow~up action on these matters):

Mr.

Carro1i;* Chairman of *the Plant Operations-Subcommittee, requeste.d that the staff keep the ACRS informed of further developments and resolution-of the hydrogen gas -buildup event - that -occl,lrr_ed at

~equoyah, Units 1 and 2, on August 22, 1990.-

Mr~ Carroil stated that the Plant Operations Sub~ -

.committee would follow.up on f-urther.developments of the new_ Standard. Technicq.l Specifications_ (S~S}

development program and the implementation of these

~new STS in certain lead plants.

• _-During the discussion of the FTOL conver-sion for Ores-. -*

~det:l, Unit* -2, the following-agre~ments were made*:

.In response t_o _a question from Dr._ Siess whether any of' the control room design reviews have been

-completed and approved by th~ staff, Mr. Zwol,tnski,,

NRR, agreed_ to provide the i!lforination later-.

Future Activities

1. -

_Future Agenda 2.. --

The Committee *agree*d* to a tentative schedule for the -

369th, January 10-12*,.1990, ACRS meeting as contained in Appendix II.

--Future Subcommittee Activities A-list of future ACRS subcommittee meetings was distributed to the Committee members (Appendix III).

The.meeting was adjourried at 12:10 p.m. on Saturday, December s;

-1990~

I

• .. j*\\.:

• ~

I.

Attendees It.. Future Agenda APPENDICES..

• .. 3'68TH.. ACRS MEETING DECEMBER 6-8, 1990

. III.*

Futur~* Subcommittee Activit'les Iv..-*

List... of *'i:>~cume*nts Provided *to the

• Conuni ttee

'\\ '-;.,

I-

'c

~

APPENDIX I 1,_,

MINUTES OF THE 368TH* ACRS MEETING DECEMBER 6-8, 1990 ATTENDEES THURSDAY, DECEMBER 6, 1990 Public Attendees William Kessler, Consumers Power Co.

David Vandewalle, Consumers Power co; Cordell Reed, Commonwealth Edison Miitc;m Richter, Commonwealth Edis.on E. D. Eenigenburg, Commonwealth Edison**

Kim Barrett, SERCH/Bechtel Alan Bearq, NUS/LIS

• D. Branne11,, Bechtel

• *y. Nagai, GPU Nuclear

• Mark Beaumont; Westinghouse Victor Ferrarini,* EAS J.

• M. Leivo, NRC consultant.'

i: Lynne *Neal, USCEA/NUMARC Norman Fletch'er,

• DOE/ ALWR C~ B. Brinkman, ABB CENP

. *. J. * :M. Simpson,. *drove Engineering Ray Ng, NUMARC:

• A.'. Neymer' NUMARC Bill Rasin,*NUMARC P. A.. Comella~ Newman & Holtzinger NRC Attendees J. Zwolinski, NRR B. Holian, NRR

p. Hartmann, R III A. Masciantonio, NRR

. 'R. *Elliott, NRR

.* B ~ S,iegel, NRR B~ Elliqtt,. NRR' F ~ Orr*,. NRR*

L. Lois,. NRR

• H~ Pastis, N~

M. Taylor, OEDO

'*. T. _Yoshida, NRR J.. Ko~ra, OCM/JC

s. Biihorn, OCM/KR R. Johnson,. NMSS D. Loosley, NMSS R.

~oyle, OCM/RB

. T~ Cox, NRR

• R., Nease; NRR

R. Gramm, NRR

• a. Grimes, NRR G. Umbro, NRR J. W~lson,.RES.

. s. Crock~tt, OCM/ FR J. Guttmann, OCM/ FR*

J. Mitchell, OCM/KC

.A. Vietti-Cooki OCM/KC R.

Rani~ri,. RES M~ Slosson, QEoo*

L.: Donatell,:' NRR.

'B. Hardin, 'RES c ~*

• At?bott, oc

• J.* * ~antaro~, RES

368th ACRS Meeting'Attendees FRIDAY, DECEMBER 7, 1990 Public Attendees Patrick Harris; SERCH Li.c/Bechtel Karen Unnerstall, Newman & Holtzinger Kevin Maha'n, LIS/NUS Steven Mirsky, SAIC Samuel E. Bryan, EG&G Ed Lozito, Virginia Power Jim Eaton, NUMARC '

Cindy Ax inn, *JEPIC

.Junji ~amaki, J~PIC Takanas Nishimoto, JEPIC.

Carole Jamerson, NEC Inc.

Warren J. Hall, NUMARC

.Robert Wadley, $PEC-Services

w.

Pug~ia, SAIC

... ~.

NRC Attendees G. Belisle, R II

w. Levis, R II D~ Fischer, NRR

• S. Diab, NRR D. Verrelli; R II*

R. *Karsch, NRR C. Rc;>ssi, NRR S. Hoffman,: NRR L. Maisl, NRR F. Rosa, NRR' J ~*. Do11ohew,* NRR J. Carter, NRR C. Liang, NRR

• J. Rogge, R I J. Macdbnald, R. I D.. Kern, R I

. L. Phillip~, NRR

. R. Wessman~' NRR s... Long,. NRR H. Pastis; NRR

. ~** M.. Taylor.. i OEDO *-,

.. _ -~

• N: Gilles, NRR- *

• M. *Reinhart,'. NRR * ~

N. Casas, NRR T _. Tj ader, NRR M. Weston, NRR K. Cotton, NRR J. Quzuo, NRR R. Emch, NRR.

I.. Yoshida, NRR.

-c.. *Harbuck, NRR

• *F. Eltawi1a,,; RES,:....

. B... Sl}eron, RES

• J. Murphy.,' RES

. R. Meyer, REs*

.R. Wright, RES J. Beckjord, RES J. Mitchell,.,

OCM/KC

• , ~

e.

APPENDIX.II MINUTES OF THE 368TH ACRS MEETING DECEMBER 6-8, 1990

. FUTURE AGENDA' Tentative Schedule for the 369th ACRS Meeting, January 10-*12, 1991 Reactor Operating Experience (Open/Closed) - Briefing and discussion regarding lessons learned. from nuclear power plant operating experience,.. including an event* that occurred at Quad cities Unit 2, on October 27,. 1990, when the reactor scrammed automatically on* "high-higp" intermediate flux during the performance.of.a special.test (turbine torsional.resonance test).

Portions of this session will be closed as necessary*t.o discuss proprietary and safeguards information applicable. to this plant.

. ACRS Bylaws (Open) - *Discuss proposed reyisions to the ACRS bylaws.

~

Final Rulemaking' 10 CFR Pa~t 55~* Fitne~s for Duty Reguirements

• for Licensed* Operators (Open) - Review and* *report _on the NRC staff's proposed final versi,an o*f the Rule related to fitness for dut~ requirements for licensed opeiators.

Proposed Resolution of- *Generic Safety Issue-29, Bolting

• oegradation or Failures in Nuclear Power Plants (Ooen) _: Review and report on the NRC staff's proposed.resolution of Generic Safety Issue-29, "B.olting Degradation or* Failures. in.. Nuclear Power Plants."

Annual ACRS Reoort to the Congress. on* the NRC Safety Research Program Copen) -

Discuss the proposed annual ACRS report to the Congress.on the NRC Safety Research Program and budget.

.Containment Design Criteria (Open) - _Dis'cuss the proposed ACRS -

report to.NRC on containment.design criteria for. future nuclea~

plants.

Meeting with the Director of the Office of Nuclear Regulatory.

Research COoen/Closed) -

Discuss matters of mµtual interest with the Director of the Office of Nuclear Regulatory Research.

Por~ions of this session will be closed as required.under exemption 9(B) to discuss potential elimination or curt~ilment

.. of specific elements of the NRC res.earch program.

Premature disclosure of the possible curtailment or elimination of any research contract could result in an inability to retain key personnel and thereby frustrate th~ Commission's ability to continue/complete affected programs effectively.

ACRS Subcommittee Activities (Open) : Hear and discuss re~ort of assigned ACRS subcommittee activities, as appropriate.

~..,

,*Jf!i8th P+CR$ Meeting Minutes II-2 Revised lO*CFR Part 20 Rule (SECY-90-387) (Open) - Briefing by the NRC staff on the proposed final version of 10 CFR Part 20,

• governing protection against radiation to provide-for a substantial increase in the overall protection of the publi6 health and safety.

Licensing and Radiation Saf:etv Reauirements

• for Larae.

Irradiators (Open)

-:-* Briefing by the NRC staff regarding.

ra.diation safety and licensing requirements ~or the use. of licensed radioactive* materials in large irradiators.

ACRS Management/Administration* (Open/Closed) *- Discuss anticipated subc:o.mmittee activities, items proposed_,for consideration by *_the full Committee,.and qualifications of.

..,,candidates for appointment to the Committee.

• Portions.. of. this.

session will be closed as necessary to discuss ihf.ormation the release* of which would repr_ei;;ent. a.ciearly unwarran.ted invasion '

. -of pei;*sonal privacy.

• Miscellaneous {Open)

Discuss matters that were not complete(j

'during previous"meetings as time and availability of 1nf ormation pe:r-mi t ~- *

.10 CFR Part 52, standa:itdization of -Nuclear Power Plants -

Briefing by *and* discussion with representatives of NqMAR-C regarding their-concerns/comments on SEC¥-90-377. * (NQTE:

Thi!:f.

item has been deferr 0ec;l.)..

~

l

e.

~68th ACRS Me~ting Minutes APPENDIX. II I FUTURE SUBCOMMITTEE ACTIVITIES

• ACRS FULL COMMITTEE & SUBCOMMITTEE MEETINGS December 7, 19 9 o.

• Thermal Hydraulic Phenomena,. December 12, 1990 ~ethesda Holiday inn,.8120 wisc~:msin Avenue, Bethesda, MD (Boehnert) I 8:30 'a.m.

The Subconuni ttee will discuss the status of the NRC staff's* program on interfacing.. systems

• loss-of-coolant accident

. (ISLOCA).

Attendance by the *fo.ilowing. is anticipated, and reservations* have been made at the*hotels indicated ~or the night' of Decelnber 11:

. Dr. Catton

• Dr. Kerr.

~* Michelson*

Mr. Ward JiYATT NONE DAYS INN(CONGR)

HYATT Dr. Wilkins*

Mr. Wylie Dr. Sullivan HOLIDAY INN HOLIDAY INN NONE Visit to St. Lucie*Nuclear Plant, December 13, 199Q, Fort.Pierce;*

FL *(Rotella).

A** visit *is: scheduled* :to observe. and*.gather.

inforjnation on fire.Protection and.mitigation featur~~.* Attendance

• by".the following. is. a,liticipated, and reservations have been made,.

at the Holiday_ Inn (407) 287-6200, ** 1209: South Federal Highway,'

Stuart, Florida.for..,the nJght of December 12:

Dr. Catton..

Mr. Michelson

.Dr. Quj,ntiere i

'l

'.Materials and Metallurgy, Jamiary,.'9,

• 1991 ~* Bethesda, Mo* (Igne).

The Sub~ommittee will rev,iew. t!le proposed resolution of Gene~ic

• Issue 29, "Bolting Degradation or Failure in Nuclear Power ':Plants.. ~*.

Attendance by the following is anticipated:

o~. Shewmon Mr. Bender Dr. Lewis Dr. Kassner Mr. Michelson

• or. Billy.

Mr. Ward*

369th ACRS Meet'ing,**January 10-12, 199*1, Bethesda, MD, 1 Room*P-llO.

Auxiliarv and Secondarv Systems, Jair!Jary 'l7, 1991,. 7920 Norfolk Avenue, Bethesda, -'MD (Rotella/Igne), 8:.30 a.m.,* Room P-110.

The Subcommittee* :will meet with the staff* and discuss *matters concerning fire protection and mitigation in nuclear poW'~r plants.

Lodging will be announced later.

Attendance by the following is anticipated:

Dr. Catton. '

Mr. Carroll Mr. Michelson

• Mr. Wylie o'r.

• Quintiere

.*,\\

/

~;.

. '

• l.c*

~'.

2 TVA Plant Liceri'si.ng and Restart, *January 24,.1991, Amberley :Suite Hot!E!l, 4880 University Drive, Huntsville, AL (Houston), 8:30 a.m.

The*SubCOJlllD.ittee will review the planned restart of Browns Ferry Unit 2 (_site visit. is planned for January 25, 1991).

At:tenda,nce by.the following is* anticipated, *and reservations have been made at*. the. Alnberley suite Hotel (205), 837~4070) for* the nights of January 23-25:.

Mr.* Wylie Mr. c_arroll Dr. Ker;r (tent:)

Mr. Ml.chelson Mr: ward Def'lieling/Fuel Pool Storage,.January 29, 1991, 792*0. Norfolk Avenue,

• • Bethesda, MD (Alderman):;, 8:30 a.in., *Room :P-11'0.

The.Subcommittee.

• will discuss th~* proposed standard review plari for reviewing safety*

. analysis reports. for dry metallic spent fuel storage casks..

Attendance.PY 'the -following is: anticipated*:.

Dr. Kerr Dr.

Si~ss Reliability..Assurance*, February 5,

• 1991,.

• 7920 No':t."folk. Avenue, *

. Bethesda, MD {Igne) ~** 8:30, a.m., Room P-110 *... The subcoJlllD.ittee :will*

d.iscuss the r~liability of. f!>afety r~lated solid :*stat¢ devices used

• in nuclear *power ;.. plants.

• Logging.will be** announced *i.ater..

• Attendance* by' *t:tie following,_*is~- anticipated:,

• Mr. car.r9ll. -.

Mr~ ~ichelson Dr.. siess

.*Mr *. Ward.

Jo'int Computers in Nuclear Power Plant.6oerations and' ;Iristrumen-.'

• tation* and Control Systems, February 6,* 199i,. 7920 Norfolk Avenue, Bethesda, MD (R'otella/El-Zeftawy), :'8:3Q.-. a.m~,. Room P-110..

The Subcommittees will discuss the use of computers and sol.id-state*

control *logic.in nuclear power plant operations..

• Lod_ging_ wil:-1 be announced :later~*.-Attendance *by the following is_ anticipated:

Dr. Lewis.*.

Dr. Wilkins.

Dr. Kerr

• Mr. Wylie

• Mr. Carrol*!

Mr.

Davi~

Dr. Catton Dr. Lipinski Mr. Michelson 370th ACRS Meeting, February 7-9~ 1991, Bethesda, MD,

~6om P-11a~

~.,

. ~

3 Improved Light Water

Reactors, Date to be determined (January/Feb~uary), Bethesda, MD (El-Zeftawy).

The Subcommittee wi,11 review the EPRI ALWR Requirements Document (Roll-µp) for the Evolutionary Designs. Attendance by the* following is anticipated:

.Mr. Wylie Dr. Catton Mr. Michelson Dr. Siess Mr. ward Joint Plant Oberations. and Probabilistic Risk As'sessment, Date to

• be determined (March, tent.), Bethesda, MD (Boehriert/Houston).

• The Subcommittees will review*the NRC staff's Action Plan to* evaluate the risk from nuclear power plant shutdown operations. Attendance

.. by the following is anticipatedf

• Mr.

Dr.

Dr.

Mr.

.Carroll*

L~wis Kerr.-**

Mich~lson

• Dr. Sies~

Mr. *Ward,

• Dr. Wilkins_

Mr. *wylie 1

~

Joint Thermal *Hy.draulic' Phenomena and core i>e:tformance,.. Date to be determined (March/April, tent.), Bethesda, MD :(Boehn*ert/Houstori).

The Subcommittees will... continue their review of the '.issues pertaining to

• BWR. core *power stabiiity.

. Attendance l:?,Y. the

_following is.anticipated:

~

'.Dr. Catton*.

Dr. Lee Dr. Kerr

.Mr..Lipinski-

• Mr. Michelson Dr. Plesset.

Dr. -Shewmon

• Mr.* Schrock Dr. wi1kins Dr. Sullivan Mr. Wylie Joint Regulatory Activities and Containment Systems, Date to b~:

determined, *Bethesda, MD (Duraiswamy/Houston) **

The.subcommittees*

wi,11 review.the proposed final revision.to.Appendix J to 10 CFR Part. 50, * "Primary Reactor Contaj,.nment Leakage Testj,.ng. for Water.:..

Cooled

• Power Re~ctors,*

11. and an. associated Regulatory Guide.

Attendance by.the following is anticipated:

Dr. Siess br. Lewis Mr. Ward Mr. Michelson Mr. Carroll Mr. Wylie Dr. Catton Dr. Kerr

~*..

9*

4 Severe Accidents, Date to be determined, Bethesda, MD (Houston).

The Subcommittee will discu.ss elements of the *severe Accident Research.

Program (SARP).

Attendance by the fallowing *

• is anticipated:

Dr. Kerr Mr. ward Dr. catton Dr. Corradini Dr. Shewmon

'Mr. Davis Dr. Siess

.Dr. Lee.

Joint Advanced Boiling* Water Reactors and *Advanced Pressurized Water Reactors, Date to be determined, Bethesda, MD (El-Zeftawy/

Rotella).* The Subcommittees will perform a-comparison betw~en the.

. Licensing Review Basis documents for the GE/ABWR and CE/system 80+

des*igns.

Attendance by_ the foliowing.j.s anticipated:

Mr. Michelson Mr.* Ward-

• Mr.* Ca_rroll Dr. Wilkins Dr *. cat ton Mr. Wylie Dr. Kerr Mr.. Costner Dr. Shewm9n

• Dr. Okrent Joint Contianment Systems and Structural Engineering, Date to :be determined,* Bethesda, MD* (Houston/Igne).. The Subcommittees will discuss containment design criteria for future plants *. Attendance*.

~y'-the following is anticipated:

Mr. Ward br. Shewmon Dr. Siess '

Mr *. Wylie*

Dr. Catton Dr. Corradini

.,,J Mr. Carroll Mr. Bender*

Dr. Kerr

APPENDIX IV MINUTES OF THE 368TH ACRS MEETING DECEMBER 6-8, 1990 LIST OF DOCUMENTS PROVIDED TO THE COMMITTEE MEETING NOTEBOOK APPLICATION OF COMMONWEATH EDISON COMPANY. DRESDEN-2 FOR A.FULL TERM OPERATING LICENSE (FTOL)

Tentative Agenda Project Status Report NUREG-1403, Safety Evaluatio:r;i Report *related to the full-term* operating license for Dresden Nuclear Power Station,

- Unit '2, Commonwealth Edison Company ACRS Report to Chai~man Palladino, dated December 13, 1982,

Subject:

ACRS Report.on the Systematic Evaluation Program Review of the Dresden Nuclear Power station, Unit 2 ACRS, Report to AEC Chairman Seaborg, dated July 17, 1970,

Subject:

Report on Dresden Nuclear Power Station Unit 2 ACRS Report to *AEC Chairman Sea.borg, dated September 10, 1969,

Subject:

Report on Dre~den Nuclear Power station Unit 2

• Presentation materials provided during the meeting PALISADES FTOL CONVERSION Tentative Agenda Status Report with attachments:

ACRS Report to AEC Chairman Seaborg, dated January 18,

.1967,

Subject:

Report on Palisades Pla~t ACRS Report to AEC Chairman Seaborg, dated January 27, 1970,

Subject:

Report on Palisades Plant

• ACRS Report to NRC Chairman Palladino, dated May 11, 1982, Subj~ct:

ACRS Report on the Systematic Evaluation.Program, Phase II, and 'its Application to the Palisades Plant Topic Evaluation suminary of NUREG-0820, Integrated Plant Safety Assessment, Systematic Evaluation*Program, October 1~82.

Presentation materials provided during the meeting

. BRIEFING.ON HIGH-LEVEL RADIOACTIVE WASTE DISPOSAL Tentative Schedule status Report Memorandum from H. Larson, ACNW Staff, for ACNW Members and Consultants D. Okrent and E. Voiland, dated July 24, 1990,

Subject:

"Rethinking High-Level Radioactive Waste Disposal," National Research Council, July 1990 Report "Rethinking High-Level Radioactive Waste Disposal -

A Position Statement of the Boqrd on Radioactive Waste Management," Commission on Geosciences, Enavironment, and Resources, National Research Council, National Academy Press, Washington, DC, July 1990 Pres~ntation materials provided during the meeting

. \\

-r.

)

• .)

...,,J>...

368th ACRS Meeting Minutes IV-2 MEETING NOTEBOOK (Continued)

CERTIFICATION OF STANDARDIZED PLANT DESIGNS Tentative Agenda*

Status Report with attachments:

I-

.SRM/M900427, dated June 18, 1990, Re:

Briefing on Evolutionary Light Water Reactor Certification Issues

_and Related Regulatory Requirements.

• I:I-ACRS.Report to NRC Chairman Carr, dated August 14, 1990,* Re:

"Level of Design Required for Design Certification Under P?trt 52" III-SRM/M900718A dated August 22, 1990, Re:. Briefing on Esseptially Complete Design Issue for Part 52

• • Submittals

• Iv-

'SECY-90-377, "Requirements for Design Certification Under 10 CFR Part 52," November.a, 1990 Memorandum *from Commissioner Remick to J.. Taylor, EQO, dated December 4, 1990,

Subject:

• SECY-90-377 -

" Requirements (or

• D~sign *certification under 10 CFRPart 52" with attachment:

~ *

• Letter *from Ber,tram. Wolfe, GE Nuclear Ene:rgy, to Chairman Carr dated Nqvember 26,.1990,

Subject:

Level 6f Qetail f6r-Staridard Plants

• Letter from Joh.n Yasinsky, Westingpouse* Electric;:

Corporation~ to Chairman *Carr, *,.dated November 28,. i.990,

Subject:

Requirements for Design* certification *un.d.er *. '

.. 20 CFR Part 52; SECY-90-377' November. 8' 1990 Memorandum.from commissioner Rogers.to J.. Taylor, EDO, dated November 30,

• 1990,

Subject:

Standard for Level of Design*

Detail Required for Design:certification -

INTERNAL'

• COMMITTEE USE ON*LY. *.-

._Chairman Carr Is staff Is "Suggested 'Questions'.. Briefing on Level of Design Detail -. Part 52*, December 7, 1990 11 INTERNAL COMMITTEE USE ONLY~--

• Lette:r from Shelby.Brewer to Chairman.Carr, dated Decembe~

4, 1990,

Subject:

' Comments on SECY-90-377, "Requirements**

for Design Cert if icatiori under 10 CFR Part 52," dat.ed

• November B, 1990

• Presentation materials provided during the meeting BRIEFING ON REACTOR OPERATING EXPERIENCE.AND EVENTS Status Report with Attachments:

SAIC-90/1372, Technical Evaluation Report~ PWR Emergency.Core Cooling System, Centrifugal.Charging Pq.mp Operability Evaluation *with a. Hydrogen**volume in** -

the.Crossover Pipe, September 6, 1990 Memorandum from P. Boehnert to J. Carroll,. ACRS, dated September 24, 1990,

Subject:

NRC-NRR Weekly Operating Reactors Events Briefing:

(19) 90-23, Septe~ber 19, 1990, Rocikville, Md.

• AEOb Technical Review.Report No.:

AEOD/T90-12, Brunswick Unit 2, Docket No. *50-324, August 199Q,..

Subject:

Loss of Off-Site Power to Cornply.with.NRC.

Regulations

368th ACRS Meeting Minutes Meeting Notebook {Continued)

IV-3 Memorandum from P. -Boehnert to J. *Carro 11, ACRS, dated August 25; 1990,

Subject:

, NRC-NRR Weekly Operating Reactors.Events Briefing:. (19) 90-21, August 22, 1999;,

• Rockville, _Md.

Presentation materials provided during*the meeting

'...LIST OF SCHEDUL~D

• ACRS FULL COMMITTEE & SUBCOMMITTEE MEETINGS -...

r

'BRIEFING.ON DEVELOPMENT OF NEW STANDARD.TECHNICAL SPECIFICATIONS Presentation Schedule Status Report. with *attachments:

Commission Policy Statement on Technical Bpecif ication

• Improvements for Nuclear Power Reactors. *.

. -~

SECY-~0-~66 dated October 29; 1990,

Subject:

• Report on

the Status **of the Technical, _specifications Improvemept*

Program

- Presentation materials.provided during the me~ting.

1~

~AFET~ -RESEARCH PROGRAM :... SEVERE ACCIDENT -:SCALING *METHODOLOGY ( SASM).

Tentative Agenda sta:tus.Report ACRS letter.. *to Chairman Carr dated April 24, * "199.0, Bubj,ect,:

Severe Accident Research Program Selected pages from Draft NUREG/CR-XXX; severe Accident Sqaling Methodology and Application to Direct Containment,

Heating, Draft No. 2, July 16,. 1990,. PROVIDED FOR INTERNAL.:*

COMMITTEE USE* ONLY..

Pr.esentation materials provided duririg the meeting.

MEETING HANDOUTS *

.* FUTURE. ACRS ACTIVITIES, 3 6 9TH ACRS MEETING, JANUARY 10-12, 19 91.

. Memorandum frpm R. P. Savio, ACRS Deputy Executive Director,*

.... '**to ACRS Members dated December 5, 1990,

Subject:

Future**

• ACRS Activities - 369th ACRS Meeting, January 10~12~: 1991 NRC STAFF RESPONSE.TO ACRS LETTER ON COMPUTER CODES AND THEIR DOCUMENTATION Memorapdum from P._ Boehnert, ACRS staff,. 'to ACRS Members dated December 6, "1990,

Subject:

~RC Staff Response.to ACRS

.Letter on Computer Codes and Their Documentation ACRS letter to J. Taylor, EDO, dated October lli 1990,

Subject:

. NRC Computer Codes and their Documentation.

Memorandum from J. *Taylor, EDO to c. Michelson, Chairman, ACRS, dated November 23, 1990,

Subject:

NRC Computer Code.s and their Documentation with enclosure:

1 1 l

~

~* -~.A.t:l:' '

• J.*tt::-'\\>

I~

i 368th ACRS Meeting Minutes

HANDOUTS {Continued)

IV-4 Letter from B. Sheron, RES, to Dr. Paul North, INEL, dated March 22, 1989 re severe accident program codes with enclosures PROPOSED*RULEMAKING TRAINING AND QUALIFICATIONS OF CIVILIAN.

NUCLEAR POWER PLANT PERSONNEL

i Memorandum from H. Alderman, ACRS Staff, to _D.;Ward, ACRS

• Human Factors subcommittee.. Chairman, dated December 7, 1990,

Subject:

• Draft Propos~d-Rulemaking Package, Training and Qualification of civilian* NPP Personnel*

Commission Policy Statement on*Training.and :Qualifications of *Nuclear Power Plant-Personnel,.March 20, 1985 Amended Commission* Policy Statement on Training and Qualifications of Nuclear Power Plant. Personn~l, *November 18' 1985 SECY-90-270 *from J. *Taylor, ~DO :to :commissioners,. dated August~' 1990,

Subject:

Response to U.S. Appeals Court's*** *',

Decision in*,Public citizen *vs. NRC

'.. ACRS CHARTER FOR 1991-1991 Memorandum from R.. Fraley ;'-'ACRS to ACRS Members,. dated..

• December,* 3, 1990,. Sub)ect:. ACRS Charter for 1991-1992.*with.. *>.

• a-etachment: i>roposeci ACRS Charter -INTERNAL COMMITTEE USE-ONLY.

OTHER DOCUMENTS

. ACCESS TO ENERGY*;* 'oecember 1900 (VoL 'ls': no. 4 ).*'

"Pervasive* beeline. of s:taff stunts* NASA,* critics Say, The New York Times, September 9, 19.90 Memorandum from J.* Hoyle*, Acting Secretary~ NRC, for c** *.

Michelson, ACRS, dated November 26, 1990,

Subject:

• staff.

Requirements - Pe.riodic Meeting with ACRS, 2: oo, P.M.,.

Thurday, November 8, 1990, Commissioners'* Conference 'Room,*

One wqite.Flint ~orth, Ifockville, Mary,land (Open to* public*

attendance)-

Letter from s. Varga, NRR to or*. Robert L. Long I.GPU Nuclear Corporation, dated November 6, 1990 1

Subject:

Clarification

• of NRC. s*taf f Position on Hydr~gen Mitigation Requirements 10 CFR 50.44 - *Oyster Creek Nuclear Generating.Station

".---'