Text

Summary of 900308-10 359th ACRS Meeting.Encl Include List of Attendees,Future Agenda & Future Subcommittee Activities
	ML20062C648
Person / Time
Issue date:	03/08/1990
From:	; Advisory Committee on Reactor Safeguards
To:	; Advisory Committee on Reactor Safeguards
References
	ACRS-2695, NUDOCS 9011020021
	Download: ML20062C648 (39)
	v • d • e

y hbkb~~0h TABLE OF CONTENTS MINUTES OF THE 359TH ACRS MEETING

- MARCH 8-10,:1990 I.

Chairman's Report (Open)...................................

1 l

a II.

Activities of the Office for Analysis and Evaluation

.i of Operational Data (AEOD)

(Open)...........................

3 i

a

.=i III.

Reactor Operating Experience (Open).........................

6 l

1 IV.

Containment Performance Improvement Program (Open).........

9 V.

Evolutionary LWR Certification-Issues (Open)...............

11 i

VI.

NRC Safety Research Program'(Op9n).........................

'14 i

VII.

Executive Sessions (Open/ Closed).......................;

14

')

A..

Report and Memorandum (Open)...........................

14 l

1.

Containment Performance Imorovement Procram -

Pronosed Recommendations for Mark II, Mark III.

Ice Condenser. and Dry Containments-(Report to Chairman Carr, dated March 13, 1990)............

14 2.

SECY-90-057. Advance Notice of ProDosed Rule-makina. "Accentance of Products Purchased for Use in Nuclear Power Plant Structures. Systems and comoonents" (Memorandum from R.

F.;Fraley, ACRS,

-.l for J.

M. Taylor, EDO, dated March 14, 1990)....

14 B.

Subcommittee Report (Closed)...........................

15 i

Appointment of_ACRS Members (Closed).............

'15 j

o C.

Other Matters ( Open)....................................

15 o

ACRS Meeting with RSK............................

15 D.

Summary / List'of Follow-Up Matters (Open)................

16 E.

Future Activities-(Open)..................-..............

20 1.

Future Agenda.........................................

20 2.

Future Subcommittee Activities.....................

20 OFFICIAL USE ONLY Supplement,Section VII.B - Dc/<fel; fold 8(f)y 9011020021 90030s PDR ACR$

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2695 PDC y 0\\\\

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. -O

~11 APPENDICES MINUTES OF THE 350TH ACRS MEETING MARCH 8-10, 1990 I.

Attendees II.

Future Agenda III.

Future Subcommittee Activities IV.

Other Documents Received e

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6 l

I w

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f l:

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'6568 Fedtr:1 Re jr / Vol. 65. No. 37 / Friday, February 1990 / Notices bh kk i

ACRS Fuu Committee Meeting

'A. Pathfinder Atomic Power Plant scheduled meeting to be advised of an b

35sth ACRS Afecting. March 010 Dismantlemer.1--The Committee will changes in schedule, etc., which may be briefed ant will comment on the have occurred.

I$Uvys NRC staff s fi adings in their safety e

e Den February tuoso.

A. Reacwr Opewting Experience off,"*$"llt(will review and (Open/ Closed}--Driefing and

*'I W"*' ""

discussion of recent events at comment on the Technical Postion on chief Pw}ectnertewBmnchNo.2.

, ope sung nucles wet plants Stabilisation/Wssie Forms, (FR Doc.90-74n Filed 2-22-ect a 45 aml y

.C.%e ACNW willinvite the epa to enraeo cons nos.ew briefing nd d cus brief them on their other Radiation n ga sides the high[

overview of the NRC AEOD reports Ctio a

he

' C.

vo t ono y Isht WaterReocior

D. Review and commerit on Safeguards; Meeting Agenda Certification Issues (OpenJ-Reports Characterization of the Yucca by and discussion of cognizant ACRS Quaternary Regional Hydrology Study in accordance with the purposes of memben and subcommittee chairmen

, Plan (tentauve).

Sections 29 and 182b. of th Atomic regarding issun identified by the NRC

E. Review of and comrnent on the Energy Act (42 t!.S.C. 2039,2232b), the staff in SECY 90-016. Evolutionary DOE /USCSTechnical Assessment Advisory Committee on Reactor Light.WaterReactor 1WR)

Certification lasues a(nd their Review (TAR). De TAR deals with.

Safeguards willbold a meeting on the evaluation of the no name fault

March &to,1990, in room P-110,7920 l

~ Relationship to Current Regulatory at the exploratory shaft facility sites.

Norfolk Avenue,Bethesda, Maryland.

Requirements

'F. Committee Activitiee-ne Notica of this meeting was published in

'D. Containmentflerformance 4

improvement Pmfrom (Open}-

Committoo will discuss anucipated the Federal Register on knuary 25,1990.

and propoeed Committee activities.

Thursdoy, Match A 1990, Room P-110, Review and comment regarding the.

future meet agenda,and 7st20 Norfolk Avenue. Bethesdo. MD.

p sed NRC contalnment organisationa matters,as rmance improvement program appmpriate-

1. "*#U "#*

1. 1. 1. 1. b or all LWR containment eexcept the BWR Mark I type con ent 19th ACNW Muting. April 2M ACRS Chairman (Open)--De ACRS

'E. Impmvement o/NuclearEbwer 199% Agenda to be announced.

Chairman willcomment on items of Plant Procurement andDedicotion of 20th ACNW Muung. Msy 2>25c current interest.

Equipment. Afaterials, andServices 199% Agenda to be announced.

g 43 g,,_,n;gg am,; off;g,yo, (Open)-Briefmg and discussion Da ted. February 20.1990.

- Analysis andEvoluotion of Opentional regarding the status of NRC staff John C. Hoyle, Doto Activities (Open)-A briefing will activities reFarding this matter be given by AEOD representatives

'F, Antic edACRSActivities Advisory committee Afonogement Officer.

regarding their activiues particularly frR Doc. 9c64181 Filed 2-22-00; 8 45 am) the nature / scope of AEOD reports on etIviti s ndi e ommitte propos for consideration by the full p

plant operat

G. ACRSSubcommittee Activities Advisory Committee on Reactor 2015 a.m.-22:15 p.m.: Reactor (Open)--Hear and discuss reports Safeguards, Subcommittee on Operating Experience (Open/ Closed}--

regardmg the status of cognizant Advanced Presourtsed Water The Committee will hold a briefm' g and subcommittee activities regarding Reactors; Date Change '

discussion of recent nuclear power plant safety reteted metters including.

operating events including the Point performanbe of valves in nuclear The ACRS Subcommittee meeting on

. Beach nuclear plant circut breaker power plants Advanced Pressurized Water Reactors design deficiencies BWR potential I

'll. Occupationo/ Rodiotion Exposure to scheduled for March 1.1990,8:30 a.m

undervoltage conditions on safety.

SAin fmm Hot Particiles (OpenJ--

rom P-422,7920 Norfolk Avenue related electrical power buses, and Briefing and discussion of proposed B(thesda, MD has been reschedul'ed for in8dequale net postive suction head of '

NRC interim action regardmg this 7tiursday March 22.1990. AU other the auxiliary feed pumps at the H. B.

,L ma t r.(tenta v

i. ems pertaining to this meeting will Robinson nuclear plant.

r smain the same as previously published

. Portions of this session wiu be closed

1. I'## s mm go$e an p act

1. [buda la the Federal Register on Wednesday, as necessary to discuss Proprietary s garding th Fsbruary 14i1990 (55 FR 5314).

formation applicable to the matters b'o RC safety research program hrther information regarding topics ing considered.

). Appointment ofACRSMembers to be discusesd. the scheduling of 2:15p.m.-2:15p.m.r Containment (Open/ Closed)-Discuss the status of sessions open to the public, whether the PerformanceImpwvement Program it appointment and qualification of meeting has been cancelled or (Open)-The Committee will review and candidates proposed for appointment to the ACRS.

rescheduled, the Chairman's ruling on report on the proposed NRC requests for the opportunity to present contalament p(rformance improvement 300th ACRSMeeting. April 5-7.1990-oral statements and the time eDotted program for contalnment types other i

Agenda to be announced.

therefore can be obtained by a prepaid than BWR Mk I pressure suppression 301st /CS Meeting. May 10-12, telephone call to the cognizant ACRS containment. Representatives of the 1990.-Agenda to be announced.

staff member, Mr. Medhat M. El.

NRC staff wiu participate.

ACNW Full Committee Meeting Zeitawy (telephone 301/492-9901) 2:15p.m.-2:45p.m.: ACRS Future between 7:30 a.m. and 4:15 p.m. Persons Jath ACNW Afecting. March 21-23, planning to attend this meeting are Aclivities (Open)--Anticipated 1990, Bethesda. MD. Items are urged to contact the above named activities of ACRS subcommittees and tentatively scheduled.

Individual one or two days before the items proposed for consideration by the full Committee will be discussed.

1

s Federal Regist

, Vol. 65 No. 37 / Friday February 23 do / Notices i

6569 3 p.in.-4.30p m.! &olutionary I.igh t.

this meeting may be limited to selected Water l'eoctor Certification Issued portions of the meeting as determined Commission's rules and regulations in to (Open)-The Committee will hear by the Chairman. information reFerding CPR chapter 1. which ere set forth in the license amendment. prior public notice reports and hold a discussion of related the time to be set aside for this purpose matters by designated ACRS members may be obtained by a prepaid telephone of the amendment was not required regarding certification issues identified cau to the ACRS Executive Director, Mr.

since the amendment does not involve a by the NRC staff in SECY.40-016.

Raymond F. Fraley, prior to the meeting. significant hazards consideration.

4:30p.in.-5.Jop.m. NRCSofety in view of the poulbility that the The Commission bas determined that Resoorch Progmm (Open}-The schedule for ACRS meetings may be result in any significant anvironmental the issuance of the amendment will not Committee will discuss the proposed odjusted by the Chairman as necessary impact end that, pursuant to to CFR ACRS report regardmg the impact of to facilitate the conduct of the meeting.

budgsting policies and practices on the persons planning to attend should check 51.22(c)(11), an environmental NRC safety research program.

with the ACRS Execullve Directorif assessment need not be prepared in Pr/ day. Aforth P.1990, Room P-110, 7!co such rescheduling would result in major cormeetion withissuance of the amendment.

NorfotA Avenue,Bethesdo MD

",Y',"fe[rInined in accordance with y

F d:30 a.m.-#:30 a.m.: Occupational

, Dposure to Rodmacurity [Open)--%e subsecuon 10(d) Pub. L s2-463 that it is

,gtion e

) the pp cation for Committee will bear a briefing by and necessary to close

'ons of this amendment deled December 4,1969, hold a discuulon with representativea meeting as noted a e to disms and (2) Amendment No.7 to Materials of the NRC staff regarding tlw proposed proprietry Information related to the Ucense No. SNM-2500, and (^,) the NRC staff interim position on matters being discussed (5 U.S.C.

Commission's letter to the licensee occupational radiation exposure to akin 552(c)(4)) and infonnation the release of dated Februa 15,1990. Allof these from hot particles (tentauve),

which would represent a clearly items are ava able for oblicinspection P-30 a.m.-4N5 ca: Appom(meni of unwarranted invasion of paracoal at the Commission's Pu lic Document ACRSMembers (Open/Ciosed)-The privacy (5 U.S.C. &&2b(c)(6)).

Room 2120 L Street, NW., Washington, Committee will discun the status of Further information regarding topics D""

appointment of a new ACRS member to to be discussed, whether the meeting Dated at Rockville, Maryland this 15th day the Committee and the qualifications of has been cancelled or reacheduled, the of February 199a candidates for this position-Chaltman's ruling on requests for the

' For the U.S. Nuclear Regulatory portions of this session will be closed opportunity to present oral statements Ccmmission.

as necessary to discuss information the and the time allotted can be obtained by Charles J. Itaushney, release of which would represent a a prepaid telephone call to the ACRS clearly unwarranted invasion of Executive Director, Mr. Raymond F, Chief. yue/ Cnle Safety BruncA Division of Indus triol and Medico: Nuclear safety, pereonal privecy, Fraley (telephone 301/492-0049),

NMSS-to a.m.-12 Noon and 1p.m. &30p.m.:

between 7:30 a.m. and 415 p.m.

[FR Doc.90-41M Filed 2-22-40; 6.45 am)

Pnpotation of ACRSReports (Open)--

Deted: February 20.1004

,,a,,a naag,,

,m The Committee will discuss the JohnC.tieyle, proposed ACRS reports to the NRC Adrhory Conunistes Measement O$cer.

regarding matters considered during this (m Doc.eH182 Filed 342-80; tes ami 10cchet Hoa. 030-0694NW/0M-2; 0so-1

' meeting.

seWMococaresee w 06te t-oM/0M-2; awemou-a; Soturdo), hforch 10,1990 Room P-110, 030-06335-OM/0M-2;030"M 004/0M-

I 7B20 Norfolk Avenue, Bethesdo, MD.

[ Docket No. T2-1) 8:30 a.m.-st.30p.m. Preparotion of Safety Ught Cwp.et al.; Oral A

y,,7,g g,,,,g ca,; g,,,,,,,,q Argument

(

Amendment to Mateetals Woonee i

p ACRS reports regarding items noted SNM-2500 in the matter of safety u ht Corporauon, et s

above, of. IDioomsburg Site Decontamination).

Procedures for the conduct of and The U.S. Nuclear Regulatory pirticipationin ACRS meetings were Commluton (the Commialon) has Notice is hereby given that,in published la the Fada=1 Regletar on issued Amendment No.7 to Materials accordance with the Appeal Board's September g7,1989 (54 FR 39504). In Ucense No,SNM-2800 band by the order of February 15,1990, oral General Electric Company for the argument on the two directed Cocordance with these procedurea, oral, receipt and storage of spent fuel at the certification motions of USR ladustries, or written statements may be presented Morris Operation, located at 7555 East Inc., and certain other parties by members of the public, recordings Collins Road, Morris, Riisola.%e (collectively identified as the USR will be permitted only during those amendment is effectiet as of the date of Companies") addressed to the Licensing portions of the meeting when a

issuance, Board's January 29 and February 8,1990, orders will be heard at 9:30 a.m. on transcript is being kept, and questions The amendment revises the Technical - Tuesday, March 6,1990, in the NRC may be asked only by members of the Specifications making administrative Persons deelring to make oral changes which do not affect, fuel receipt, Public Hearing Room, Fifth Floor East.

Committee, its consultants, and staff.

handling, and storage safety.

West Towers Building. 4350 East. West statements should notify the ACRS The application for the amandment Highway. Bethesda, Maryland, Exemtive Director as far in advance as complies with the standards and For the APPealBoard.

practicable so that appropriate requirements of the Atomic Energy Act Deted: February 16.1990.

crrangements can be made to allow the of1954, as amended (the Act), and the Bartaara A.Tompkins, necemary time during the meeting for Commission's rules and regulationa.%e Secretaryto the AppealBootst.

such statements. Uee of still, motion Commission has made appropriate (FR Doc. 9o-4178 Filed 242-00; 4:45 mm) picture and television cameras during findings as required by the Act and the sinneo coot rmew

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c, UNITED STATES

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'n NUCLEAR REGULATORY COMMISSION

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ei ADVISORY COMMITTEE ON REACTOR SAFEGUARDS

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WASHINGT ON,0. C. 20655 k...* /

e February 28, 1990 SCHEDULE AND OUTLINE FOR DISCUSSION I

359TH ACRS MEETING MARCH 8-10, 1990 Thursday. March 8.

1990. Room. P-110, 7920 Norfolk Avenue. Bethesda Md.

1) 8:30 -

8:45 A.M.

Chairman's Pemarks (Open) 1.1)

Opening Remarks (CM/GRQ) l 1.2)

Items of current interest (CM/RFF) 2)

8:45 - 10:00 A.M..

Office for Analysis and Evaluation i

of Operational Data-Activities.(Open).

2.1)

Briefing by representatives of.

AEOD-regarding office activities, particularly the nature / scope of AEOD. reports on analysis and evaluation of nuclear: power plant operating events (HWL/HA) 10:00 -

10:15 A.M.

Break

3) 10:15 -

12:15 P.M.

Reactor-Oneratina Excerience (Opon/ Closed) 3.1)

Briefing and discussion of=recent nuclear power plant. operating ex-perience including: (JCC/PAB) 3.1-1) 125V DC system circuit-breaker design problem at Point Beach Units:1.and 2, 11/7/89 3.1-2)

Potential ~LPCI swing. bus undervoltage failure (gen-eric to'BWRs),. 10/12/89 3.1-3).

Inadequate NPSH of aux-iliary feedwater pump at-Robinson Unit 2, 8/16/89 (Portions of this session will be closed' as required to discuss Proprietary In-formation applicable to the matter being.

considered.)

12:15 -

1:15 P.M.

Lunch

2 L.

1 4) 1:35 -

2:15 P.M.-

Containment Performance Innrovement Pro-gram (Open)

.4.1)

Consents by ACRS subcommittee chairman regarding-proposed NRC Containment Performance Improve-ment Program for BWR Mark II and Mark:III containments and PWR ice condenser and dry containments

- l (DAW /MDH) 4.2)

Meeting with representatives of i

the NRC Staff

.4 3) 2:15 -

2:45 P.M.

ACRS Puture Activities (Open) 5.1)

Discuss-anticipated ACRS subcom-mittee activities (RPS/RFF) 5.2)

Discuss items proposed for con-sideration by the full Committee (CM/RPS) 2:45 -

3:00 P.M.

Break

6) 3:00 -

4:30 P.M.

_ Evolutionary LWR Certification Issues (Open) 6.1)

Hear and discuss reports from designated ACRS members regarding-issues identified by the.NRC staff in SECY-90-016, Evolutionary Light

- Water Reactor (LWR) ~ Certification-Issues and-Their Relationship to 4

Current Regulatory Requirements 1

(CM/CJW, et al./MME)-

7) 4:30 -

5:30 P.M.

NRC Safety Research Prosram (Open).

7.1)

Discuss proposed ACRS comments /

regarding the impact of budgeting policies and practices on the NRC safety research program-(IC/SD)

Friday. Marc'M'9 -&nso Room P-110, 7920 Norfolk Avenue. Bethesda. Md.

8) 8:30 -

8:45 A.

intment of ACRS Members (Open/ Closed) 8.1) uss the status of appointment

-of ca ates nominated-as Committee members (

"*"L)

(Portions of this ses will be closed as necessary to discuss ation the release of which would represe clearly unwarranted invasion of pe nal privacy.)

o l

3 i

- l 9) 8:45 - 11:00 A.M.

Preparation of ACRS Reoorts (Open) 9.1)

Proposed ACRS comments / report on evolutionary LWR certification--

issues (CM/CJW/MME)

[

9.2)-

NRC safety research program.

J (IC/SD)

10) 11:00 - 12:00 Noon ACRS St(gommittee Activities (Open) 10.1)

Hear and discuss the status of subcommittee activities in safety related areas including Mechanical Csaponents Subcommittee meeting on 3/7/90 (CM/EGI)~

12:00 -

1:00 P.M.

Lunch

11) 1:00 -

5:30 P.M.

Precaration of ACRS Recorts (Open) 11.1)

Containment Performance Improvement.

1 Program (DAW /MDH) i 11.2)

Continue discussion of proposed ACRS reports Saturday, March 9.

1990. Room P-110. 7920 Norfolk Avenue.-Bethesda, Md.

12) 8:30 -

12:30 P.M.

Preoaration of ACRS Recorts 12.1)

Continue discucsion of proposed ACRS reports to the NRC as needed l

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e I

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1 I

i 3

1 l

359th ACRS Agenda Revised:3/8/90 Friday. March 9. 1990. Room P-110. 7920 Norfolk Avenue. Bethesda. Md.

I

8) 8:30 -

8:45 A.M.

Anpointment of ACRS Members (Open/ Closed) 8.1)

Discuss the status of. appointment l'

of candidates nominated as Committee i

members (CM/MFL) l (Portions of this session will be closed as necessary to disc 9ss information the release of which would represent a clearly unwarranted invasion of personal privacy.)

9) 8:45 - 11:30 A.M.

Preparation of_ACRS Rooorts (Open) 9.1)

HRC safety research program i

9.2)

Containment Performance Improvement Program (DAW /HDH) i 9.3)

Proposed ACRS comTeats/ report on evolutionary LWR r;ettification issues (CM/CJW/MME)

10) 11:30 - 12:00 Noon ACRS Subcommittee Activities (Open) 10.1)

Hear and discuss the status of subcommittee activities in safety

(

related areas including Mechanical i

Components Subcommittee meeting l

on 3/7/90 (CM/EGI) 12:00 -

1:00 P.M.

Lunch

11) 1:00 -

5:30 P.M.

Precaration of ACRS ReDorti (Open) 11.1)

Continue discussion of proposed ACRS reports l

Saturday. March 9. 1990. Poom P-110. 7920 Norfolk Avenue. Bethesda. Md.

12) 8:30 -

12:30 P.M.

Preparation of ACRS ReDorts l

12.1)

Continue discussion of' proposed ACRS reports to the NRC as needed l

l l

b

~.

MINUTES OF THE 359th ACRS MEETING MARCH 8-10, 1990 The 359th meeting of the Advisory Committee on Reactor Safeguards (ACRS) was held at Room P-110, 7920 Norfolk Avenue, Bethesda, Md.,

between March 8-10, 1990. The purpose of this meeting was to discuss and take appropriate actions on the items listed in the attached i

agenda.

The entire meeting was open to public attendance with the exception of a portion of the meeting that dealt with the discussion of the qualificatior.s of candidates proposed for consideration as ACRS members.

A transcript of selected portions of the meeting was kept and is available in the NRC Public Document Room.

(Copies of the transcript are available for purchase from Ann Riley & Associates, Ltd., 1612 j

K Street N. W.,

Washington, D.C.

20006.)

I.

Chairman's Renort (Open)

)

(NOTE:

Mr. R. F. Fraley was the Designated Federal Official for this portion of the meeting.)

Mr. Michelson, the full Committee Chairman, convened the meeting at 8:30 a.m. with a brief summary of the planned meeting schedule and the provi:2 ions under which the discussions were to be held.

He stated that the Committee had received written comments from the Electric Power Research Institute (EPRI) regarding the evolutionary light water reactor certification issues identified by the staff in SECY-90-016, " Evolutionary Light Water Reactor (LWR) Certification Issues and their Relationship to Current Regulatory Requirements."

He said that the Committee had received no requests for time to make oral statements from members of the public.

Items of Current Interejiit l

Mr.

Michelson stated that the following items are of current l

interest:

o The NRC has removed the following plants from the list of

" Problem Facilities":

Peach Bottom Units 2 and 3 Pilgrim Turkey Poir.: Units 3 and 4 o

The following plants are authorized to operate with close NRC monitoring i

359th ACRS Meeting Minutes 2

i l

Calvert Cliffs Units 1 and 2 Nine Mile Point Units 1 and 2 Surry Units 1 and 2 o

Browns Ferry Units 1, 2,

and 3, that have been shut down since 1986, need to get NRC authorization to operate, and NRC will monitor closely the operation of these units.

i o

The following plants have' been identified as receiving consistently good performance ratings:

1 Callaway Kewaunee Prairie Island Yankee Rowe o

The following plants have received honorable nention for good performance:

Susquehanna St. Lucio Diablo Canyon o

The following changes in appointment of senior executives at the NRC have been made:

Mr. James Sniezek, Deputy Director, Office of Nuclear Reactor Regn ition (NRR), has been appointed as the Deputy Executive Director for Operations (EDO) effective March 1, 1990.

Mr. Frank Miraglia, Associate Director for Inspec-tion and Technical Assessment, NRR, has been appointed as the Deputy Director, NRR, effective April 1, 1990.

Dr. Denwood Ross, Deputy Director, Office of Nuclear Regulatory Research (RES), has been appointed as the Deputy Director for Office for Analysis and Evaluation of Operational Data (AEOD) effective March 1, 1990.

Mr. Clemens Heltemas, Deputy Director, AEOD, has been appointed as the Deputy Director., RES, effective March 1,

1990.

Mr.

Thomas Martin,

Director, Division of Reactor Safety, Region I, has been appointed as the Regional Administrator, Region I.

t

s 359th ACRS Meeting Minutes 3

5 SECY-90-046, Economic Incentive Regulation of Nuclear Power o

Plants, dated February 13, 1990, contains some interesting information and the Committee members may want to peruse the contents of this doc'iment at their convenience.

o In SECY-90-061, Implementation of TMI Action Plan Items, dated February 22, 1990, the staff states that over 98 percent of the TMI Action Plan requirements have been implemented at licensed plants, and significant progress has been made in implementing the remaining 207 open issues.

o In SECY-90-055, PIUS Design Review, cated Febt.uary 20, 1990, the staf f states that ASEA Brown Boreri has requested a licensability review of the PIUS design.

The >>*ff has proposed a conceptual design review within the existing resources allocated for the review of Advanced Passive LWR designs.

II, hgtivities of the Of fice for Analysis and Evaluation of Operational Data (AEODL (Open)

(NOTE:

Mr. H. Alderman was the Designated Federal Official for this portion of the meeting.)

Mr. Rosenthal, AEOD, stated that they plan to brief the Committee on the status /results of the following AEOD studiest o

Thermal stratification in Nuclear Power Plant Piping Systems Safety Equipment Outages / Failures at the Zion plant o

o Solenoid Valve Failures Thermal Stratification in Nuclear Power Plant Picina Systems Dr. Su, AEOD, discussed briefly the ' AEOD study related to Thermal Stratification in - Nuclear Plant Piping Systems.

He stated that thermal stratification is a condition in which two streams of fluids of dif ferent temperatures flow in separate layers without appreciable mixing.

This condition exists when the flow rate. is low and temperature difference is high.

Dr. Su cited the pressurizer surge line as an example to illustrate thermal stratification.

He noted that during heatup the temperature in the pressurizer can be as high as 400 degrees Fahrenheit while the hot leg temperature is 120 degrees Fahrenheit or lower.

The surge line is about 8 to 16 inches in diameter and is 40 to 80 feet long.

The flow rate in the surge line is few gallons per minute; this flow rate is small compared to the large size of the surge line.

These 1

i e

359th ACRS Meeting Minutes 4

conditions, that is, high temperature difference and low flow, lead to thermal stratification in the surge line.

Dr. Su stated that there are two categories of thermal stratifica-tion, global and cyclic.

Global stratification results in low cyclic I

movement and high stress which can cause pipe movement and damage to pipe supports.

This type of stratification is stable and the temperature changes are very slow with respect to time.

1 Cyclic thermal stratification can vary f airly rapidly with time.

Cyclic stratification can cause a pipe to be exposed rapic.ly to hot and cold temperatures causing futique, and potentially a pipe crack.

Thermal stratification was identified as the cause of a feedwater line crack at D.

C. Cook in 1979.

This led to investigations at other plants and 14 plants have reported varying degrees of pipe cracks at approximately the same location in feedwater lines.

He stated that Trojan, Turkey Point, Beaver Valley, and Diablo Canyon plants experienced cracks at surge lines as a result of thermal stratification.

]

I Mr. Carroll pointed out that a typical feedwater line has a thermal i

sleeve to protect the nozzle.

The thermal sleeve connects directly to a feedwater ring sparger.

There is a potential leakage path around the thermal sleeve due to the fact that the thermal sleeves are press-fitted.

Small amounts of cold feedwater intermittently heating and cooling the walls of the vessel can cause thermal fatigue cracks.

Dr. Su stated that, based on the results of the study, they have L

reached the following conclusions:

o Thermal stratification results in significant stress and thermal i

fatigue in system piping.

o Thertaal stratification could potentially occur in many interfacing systems.

o A long-term solution is required.

A two-year program is being conducted by EPRI and is sponsored o

by PWR and BWR owners groups.

i Safety Equiement Outaces at Zion Mr. Manning, AEOD, discussed an analysis of outages / failures of plant equipment at the Zion plant.

He stated that Zion submitted four event notifications to the NRC between November 22-23,

1983, i

l k...,. -

359th ACRS Meeting Minutes 5

.d concerning outages of an emergency service water system pump and f ailures/ outages of diesel generators. He noted that the combination of equipment that failed and the way the equipment failed could make the plant more vulnerable to loss of offsite power.

Consequently, AEOD performed an analysis using accident sequence precursor methods to estimate thet o

Overlap interval of concurrent failures or outages.

o Likelihood of station blackout core damage scenarios.

Mr. Manning stated that the Zion plant has five diesel generators.

Two are dedicated to Unit 1 and two to Unit 2.

One diesel generator is a swing and can feed either Unit 1 or 2.

There are six emergency service water pumps.

Given a loss of offsite power, a diesel can drive only one of these pumps.

Each diesel is hard-wired to buses that are hard-wired to particular pumps.

The swing diesel can feed one pump in Unit 1 or 2.

Mr. Manning stated that during this event Unit 1 was in shutdown and getting ready for startup.

He said that the following assumptions were used in the analysis:

Unit i diesel 1A was in maintenance for a rod-bearing problem.

Unit 1 diesel IB was in maintenance for testing.

Swing diesel 0 indicated high-bearing temperature.

Unit I diesel 2A had a gas test connector leak.

Unit 2 diesel 2B was available.

Given the conditions of the diesels, it was postulated that with a loss of offsite power diesel generator "0"

would overheat its bearings and fail, 2A would also fail, and only diesel generator 2B would be available.

If a loss of offsite power occurred at this time, the plant would only be able to function for a short time, estimated to be about one-half hour.

l Mr. Rosenthal pointed out that this analysis was illustrative of a technique of tryinq to look at multiple events within a time period and see if there is n ore significance than with individual events.

Mr. Manning stated te at the analysis has been submitted to the Zion plant manager for co'aent.

The staff has not yet received a reply from Zion.

Solenoid Valve Failures owing to lack of time, the briefing on the status of the AEOD study related to solenoid valve failures has been deferred to the April 5-7, 1990 ACRS meeting.

Subsequently, it was deferred to the May 10-12, 1990 ACRS meeting.

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359th ACRS Meeting Minutes 6

III.

Egaetor oneratina Exoerience (Open)

(NOTE:

Mr. P. Boehnert was the Designated Federal Official for this portion of the meeting.)

Mr. Carroll, Chairman of the Plant Operations Subcommittee, noted that the three items selected for Committee review have as their common theme an illustration of problems in system / component design.

Mr. Rossi, NRR, said t' t NRR wou7d brief the Committee on the following three events

Discovery of a de gn-related problem for the 125V DC circuit o

breakers at the Point Beach plant.

A generic concern with the potential failure of the swing bus o

in the low-pressure coolant injection-(LPCI) systems of certain BWRs, given an undervoltage condition, o

Identification of a potential for inadequate net positive suction head (NPSH) for the pumps in the auxiliary feedwater (AFW) system at the H.

B. Robinson plant.

Mr. Rossi said that NRR would also respond to questions posed by Committee members during the discussion of certain operating events at the January 11-12, 1990 ACRS meeting.

Desian-Related_ Problem for the 125V DC Circuit Breakers at Point Beach Units 1 and 2 Mr. Kendall, NRR, stated that the key factors associated with this event are:

o During a selfoinitiated safety system functional inspection, the licensee discovered that the breakers in the 125V DC system did not have instantan60us (short circuit) fault protection, but had only thermal fault protection.

o The concern is that a short circuit fault would not be cleared and could propagate such that the entire 125V DC system could be compromised.

o The breakers with inadequate protective devices have been replaced.

o No generic implications were found.

o Escalated enforcement action is pending; an inspection of the plant's electrical system is scheduled for the near future.'

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359th ACRS Heeting Minutes 7

l In response to a question from Mr. Michalson, the NRR staff said that the breakers were originally ordered without the proper fault protection which is a violation of standard design practice.

Mr.

i Wylie said use of such breakers is probably a violation of IEEE Standards.

Mr. Michelson said this event highlights the issue of NRC's accep-tance of questionable design basis parameters.

Mr. Rossi noted that NRC's licensing review does not extend to this level of detail.

He said that NRC relies on the use of Bulletins, Information Notices, and Generic Letters to address issues such as this.

Mr. Carro13 asked how the staff knows that this is not a generic problem.

The NRR staff said that a check of Point Beach's sister plants showed no use of such defective breakers.

Also, a cursory check of some near term operating license plants revealed no such problems.

Dr. Kerr inquired about the pending enforcement action.

The staff indicated that apparently the licensee did not either take prompt corrective action or submit a justification for continued operation until about 10 months after discovery of the problem.

Potential Failure of the Swina Bus in the LPCI Systems of Certain BWRs Mr. Green, NRR, stated that this problem was identified by the Monticello plant licensee following NRC inquiry of an unrelated concern with the swing bus at the Fermi plant.

A postulated single failure (degradation of a diesel generator voltage regulator) could i

affect the transfer of the LPCI swing bus, Given a LOCA, coincident with loss of offsite power, both LPCI systems and one train of core spray system would be unavailable; also, one diesel generator would be degraded.

A number of conditions must exist for the above scenario to occur.

The key one is that voltage must degrade to between 50-80% of nominal.

Mr. Green stated that nine BWR plants were potentially subject to this concern.

Upon evaluation, only four were found to be actually affected (Dresden 2-3, Fermi 2, Monticello, and Quad Cities 1 & 2).

The fix chosen by Monticello was to install relays to ensure a switchover at higher degraded voltages (580%).

NRR is reviewing the modification plans for the remaining affected plants.

Mr. Carroll observed that the Monticello plant is of the same vintage as Point Beach; further, they both utilized the same architect engi-neer.(Bechtel) who was responsible for the design of these systems.

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i Inadequato NPSH of Auxiliary Feedwater Pumo at H.

B. Robinson Unit

?

Mr. Thorpson, NRR, stated that the licensee identified this concern during a late-1986 self-initiated safety system functional inspection of the AFW system at H. B. Robinson.

Specifically, it was determined that the APW pumps could fail by cavitation due to inadequate NPSH.

The lack of adequate NPSH was due to the suction feed pipe (common to the three pumps) being undersized.

Cavitation of the pumps would occur if: all three pumps were started simultaneously (as is required

)

upon a LOCA signal), and the condensate storage tank water level is at its minimum, per technical specifications.

This problem hac existed since initial plant operation.

of particular interest for this event, is that its discovery was delayed due to the licensee's management taking a

narrow interpretation of system " operability" when confronted with degraded flow conditions upon testing.

Specifically, while the test results showed adequate system flow, the fact that individual pump flows were below minimum requirements was overlooked.

NRR said that there was d lack of high-level management attention to this issue.

Corrective actions include:

replacement of the undersized (6-inch ID) pipe with a 12-inch line; redefinition of the operability parameters for the system; and licensee actions to increase management involvement with problems.

NRC had dispatched an Augmented Inspection Team (AIT) for this item.

Among the follow-up items under staff revie.w is the issue of requiring simultaneous start of all AFW pumps, During the discussion that followed, Mr. Rossi said the central issue underlying this event is how the NRC should address the discovery of deficiencies that originated in the original plant design bases.

He y

said the Staff is investigating what, if anything, should be done here.

NRR Response to Follow-UD ouestiong Mr. Fisher provided the staff's response to a set of questions posed by committee members.during the last operating Events briefing held at the January ACRS meeting.

A paraphrase of each question and the NRR response are given below.

Q1 Has there been a history of problems with backflow through the HPCI systems?

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Yes; this problem has been seen in both PWR and BWR high pressure injection emergency core cooling systems, but the event frequency has declined significantly since 1981.

c Qi Are licensees monitoring the temperature of these HPCI systems to protect against water hammer events?

M Yes; temperature is being monitored, as are other pre-ventative measures.

i Q1 Has Westinghouse developed emergency operating procedures to address loss of decay heat removal (DHR) in Modes _4-67 h

The Westinghouse owners Group is developing procedures to address loss of DHR during mid-loop operations.

The Committee requested that the staff provide a briefing on the status of their efforts related to the development of emergency operating procedures for the shutdown modes of operation (Modes 3-6).

Mr. Carroll complimented the staff on both the high quality of the presentations and the completeness of their responses to the follow-up questions.

IV.

Containment Performance Imorovement Procram (Open)

(NOTE:

Mr. D. Houston was the Designated Federal Official for this portion of the meeting.)

Mr. Ward, Chairman of the Containment Systems Gubcommittee, reviewed briefly the Committee's previous activities in regard to BWR Mark I containments.

He indicated that the NRC _ staf f has now proposed closure of the Containment Performance Improvement (CPI) program related to BWR Mark II, Mark III, ice condenser, and large dry containments.

He stated that the containment Systems Subcommittee had met with the staff on February 6,

1990 to discuss a draft Commission Paper and a proposed supplement to Generic Letter 88-20,

" Accident Management Strategies for Consideration in the Individual Plant Examination Process."

He indicated that the staff had been receptive to suggestions offered at the subcommittee meeting and had used them to improve the proposed supplement.

Dr. Beckner, RES, reviewed the past activities / recommendations of the CPI program for the BWR Mark - I containments and discussed the proposed recommendations for Mark II', Mark III,-ice condenser, and

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.6 359th ACRS Meeting Minutes 10 large dry containments.

The recommendations, noted below, are intended to be considered in the individual plant examination (IPE) process:

Venting, alternate ways to cool the suppression Mark II pool and the Mark I improvements.

Backup power to hydrogen igniters and the Mark Mark III I Improvements.

It LcorlengI - Backup power to hydrogen igniters.

dy.g -

Hydrogen detonation (screening method).

Dr.

sckner indicated that the above recommendations would be pr

. led to the licensees in the proposed supplement to Generic Lt-y r 88-20 without the benefit of technical reports being developed by "ue NRC contractors.

The reports apparently will be ready about J

the same time as the anticipated issuance of the supplement (about i

June 1990).

lie further indichted that the proposed supplement would be issued for information only and would contain no new requirements.

He stated that with the issuance of the supplement, the CPI program would be considered complete.

Mr. Michelson asked how the staff had evaluated the capability of ensuring isolation of containment penetrations under severe accident conditions.

Dr. Beckner stated that the staff had relied heavily on the studies reported in NUREG-1150 and supplemented by a number of other PRAs.

Dr. Catton expressed a concern in regard to hydrogen igniters.

He based his concern on a portion of the National Research Council report " Technical Aspects of Hydrogen Control and Combustion in i

Severe Light-Water Reactor Accidents."

He suggested that the staff read this report and use this report as a reference in the proposed supplement.

Mr. King, RES, responded that the staff would censider doing this.

I.

Dr. Catton also expressed a concern about venting of BWR contain-ments, all of which have suppression pools.

His concern was in regard to the release of fission products from a saturated pool once the overpressure has been reduced by venting.

Dr. Beckner stated that, in some accident scenarios, containment venting would be done prior to fuel damage so that there would be no fission product buildup in the pool.

Dr. Bockner discussed briefly the accident management strategy under consideration for depressurization of' reactor coolant systems at PWRs to reduce the probability of high-pressure core melt ejection that-1%

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.A 359th.hCRS Meeting Minutes 11 could lead to direct containment heating (DCH).

He indicated that a drawback to this strategy is the potential release.of a large quantity of hydrogen into the containment.

The staff is considering the potential hazards of this release as they look at depressurization as a generic recommendation.

The staff has not arrived at any apparent conclusions in regard to local detonations or stratification of hydrogen.

In regard to the contractor reports mentioned by Dr. Beckner, Dr.

I Catton asked about the availability of these reports in draft form.

Mr. King indicated that they would supply these to the committee when they reach a stage that RES feels is fairly complete and accurate.

The Committee issued a report to the Commission on this matter, dated March 13, 1990, endorsing the staff's approach and the proposed I

supplement to Generic Letter 88-20.

The Committee recommended that the staff caution the licensees not to focus exclusively on the set of issues raised by the CPI program.

This report is discussea in Section VII.

V.

Evolutionary LWR Certification Issues (Open)

(NOTE:

Dr.

M.

El-Zeftawy was the Designated Federal Official for this portion of the meeting.]

Mr.

Michelson provided a preamble, stating that the staff has identified 15 significant issues in SECY-90-016, " Evolutionary Light Water Reactor (LWR) Certification Issues and Their Relationship to Current Regulatory Requirements," as fundamental to agency decisions on the acceptability of evolutionary LWR designs.

During the February 8-10, 1990 ACRS meeting, the Committee heard presentations by and held discussions with the staff regarding these 15 issues.

Subsequently, the Committee assigned these issues to various l

Subcommittee Chairmen / members for review and comment.

The cognizant Subcommittee Chairmen / members were requested to develop comments / recommendations on the assigned-issues and submit them to the full Committee for consideration during the March 8-10,1990 ACRS meeting.

The members were also requested to identify any new issues that they believe should be considered by the staff for the evolutionary LWRs.

During this meeting, the Committee will discuss the comments / recommendations proposed by cognizant Subcommittee Chairmen / members on these issues and will try to complete a report to the Commission.

The Committee discussed the comments / recommendations proposed by various Subcommittee Chairmen / members regarding the 15 evolutionary LWR certification issues.

The Committee agreed with.the proposed comments / recommendations related to 10 items, subject to editorial changes.

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359th ACRS Meeting Minutes 12 Owing to lack of time, the Committee deferred discussion of the proposed comments / recommendations on the following five items, and any potential new issues, until the April 5-7, 1990 ACRS meeting:

o Evolutionary LWR Public Safety Goals o

Mid-loop Operation o

Station Blackout o

Containment Performance o

Equipment Survivability Mr. Michelson stated that, during the March 27, 1990 meeting of the Joint Extreme External Phenomena / Severe Accidents Subcommittees, he would like to discuss with the staff the fire protection provisions for evolutionary LWRs to gather additional information.

The Com-mittee did not raise any objection.

Mr. McCracken, NRR, agreed to provide a presentation on this matter during this meeting.

l In addition, the Committee decided to discuss the following issues with representatives of the NRC staff and industry (as appropriate) during the April 5-7, 1990 ACRS meeting:

o ABWR Containment Vent Design o

Equipment Survivability In response to a question from the Committee, Dr. Miller, NRR, stated that SECY-90-016 was developed in response.to a request from the Commission that the staff identify those policy issues related to evolutionary LWRs where they plan to go beyond the current regulatory requirements.

The Commission wants to take a position on such policy issues as soon as possible so as to preclude any potential delay in the staff's review of the evolutionary LWR designs.

1 Mr. Carroll suggested that the commission instruct the staff to place more emphasis to complete its review of the EPRI ALWR Requirements Document.

Dr. Siess asked to what extent GE, Westinghouse, and CE would abide by the requirements delineated in the EPRI ALWR Requirements Document.

Dr. Miller stated that GE has_previously stated that it would try to comply with the EPRI ALWR requirements.

However, if it!

plans to deviate from some of the EPRI requirements, it would document the bases for such deviations.

Dr. Siess stated that he'would like to hear from representatives of GE, Westinghouse, and CE as to whether they would comply with the EPRI ALWR requirements.

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359th ACRS Meeting Minutes 13 In response to a question from Dr. Kerr, the staff stated that they plan to brief the appropriate ACRS subcommittee on the decoupling of siting and source term.

Dr. Lewis expressed some concern that the staff is reviewing the evolutionary LWR designs against criteria that have not yet been approved by the Commission, such as the severe accident policy goals for which the staff requested approval in SECY-89-102.

He indicated that the commission should decide on the acceptability of these goals before the staff and the ACRS evaluate the acceptability of the other 14 issues.

The Committee decided to include a preamble to its report to the Commission expressing this concern.

Dr. Lewis was assigned the task of writing the preamble.

Dr. Kerr commented that the staff's position regarding the source term issue for the evolutionary LWRs is ill-defined and relies heavily on engineering judgment.

Dr. Kerr noted that, for the anticipated transients without scram (ATWS) issue, he would rather have the vendors show that they can ride out an ATWS as an alternative to diverse logic in the scram system.

He indicated that it would be feasible to demonstrate that PWRs could ride out an ATWS and that such a demonstration was preferable to installation of a diverse logic system.

Dr. Shewmon commented that the staff is reviewing against a criterion that addresses noncredible events.

He indicated that only one-fourth of the core could be ejected and it is incredible to form a nozzle in the lower head of a vessel with no bottom penetrations (such as the CE design).

Mr. Carroll was concerned that the vent proposed on the ABWR design may increase risk through spurious actuation or malfunction during operation, and noted that the ACRS did not review the vent installed in the Pilgrim plant.

Mr. Michelson encouraged the members to identify any other issues that they may believe should be considered for the evolutionary LWRs.

Mr. Michelson requested that EPRI provide its optimization list that' identifies safety issues related to evolutionary LWRs. A representa-tive of EPRI agreed to provide this list.

Mr.

Michelson suggested that the members review the comments /

recommendations related to the 10 LWR certification issues finalized by the Committee during this meeting with respect to the definition of "how safe is safe enough" included in the Commission's Safety Goal Policy.

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359th ACRS Meeting Minutes 14 After further deliberations, the committee decided to continue its discussion of the evolutionary LWR certification issues and an associated ACRS report to the Commission during the April 5-7, 1990 ACRS meeting.

i VI.

NRC Safety Research Procram (Open)

The Committee discussed a proposed report to the Commission on the adequacy of the NRC Safety Research Program Budget and the impacts of a continually dwindling NRC research budyut on the regulatory process.

Several members of the Committee felt that the report needs to be revised and provided comments and suggestions for use in revising the report.

The Committee suggested that Dr.

Catton, Chairman of the Safety Researen Program Subcommittee, prepare another draft taking into account the comments / suggestions provided by the Committee members and submit it for consideration by the Committee during the April 5-7, 1990 ACRS meeting.

VII.

Egecutive Sessions (Open/ Closed)

A.

Reoort and Memorandum (Open) 1.

_ Containment Performance Imorove.'ent Procram Proposed Recommendations for Mark II. Mark III. Ice Condenser, and Dry Containments (Report to ChairmLn Carr, dated March 13, 1990).

The Committee endorsed the approach proposed by the staff to provido technical insights and information, resulting from the containment Performance Improvement (CPI) program, i

to licensees (with plants that use Mark II, Mark III, Ice Condenser, and Dry Containments) in a Supplement to Generic Letter 88-20.

The Committee endorsed this Supplement and agreed with the staff that the CPI program can now be terminated.

The Committee recommended that the staff-caution the licensees not to focus exclusively on the set of issues raised by the CPI program.

2.

SECY-90-057.

Advance Notice of Prooosed Rulemakina.

" Acceptance of Products Purchased for use in Nuclear Power Plant Structures. Systems and Components" (Memorandum from R.

F. Fraley, ACRS, to J. M. Taylor, EDO, dated March 14, 1990).

Consistent with the Committee's decision, Mr. Fraley has informed Mr. Taylor that the Committee has decided not to review t h'.

above mentioned ' Advance Notice of Proposed Rulam. king.

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359th ACRS Meeting Minutes 15 B.

Subcommittee ReDort (Closed) o Apoointment of ACRS Members (Closed)

Contained in Official Use Only Supplement.

C.

Other Matters (Open) o ACRS Meetina with RSK Mr.

Fraley informed the Committee that the RSK has confirmed the following itinerary for the ACRS/RSK meeting and related facility visits:

Arrive at K61n, Germany j

June 20. 1990 June 21-22, 1990 -

Meeting regarding HTR-Module and l

MHTGR (Julich, Germany)

No Meeting June 23. 1990 Travel to Philippsburg area (near June 24. 199.Q Mannheim)

Visit to 2D/3D Test Facility near June 25. 1990 Mannheim 2.une 26-27. 1990 -

Meeting regarding LWR Issues Visit to Philippsburg Nuclear June 28, 1990 Station i

June 29. 1990 Travel to Frankfurt and Return to U.S.

l Tonics Identified for Discussion Modular HTR Items

- Severe Accident Scenarios (Ward)

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- Containment Design / Performance Requirements (Ward) l

- Core Heat Transfer (Catton)

- Core Physics (Catton)

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359th ACRS Meeting Minutes 16 4

LWR Items Severe Accident Manacement (Kerr)

- Role of Analytical Tools in Accident Management (Catton)

- Bleed and Feed Cooling i Primary and/or Secondary (Catton)

- Containment Venting Requirements (Ward)

J Performance of Motor Ooerated Valves (Michelson)

- Requirements for Isolation of System Breaks (Michelson) i

- Testing Requirements, In-Situ vs. Bench Testing (Michelson)

Firo Protection Provisions (Michelson)

- Impact of Inadvertent Actuation-(Michelson)'

Plant Life Extension Beyond 40 Years (Lewis)

- Equipment Aging (Wylie)

- Pressure Vessel Annealing (Shewmon)

- BWR Stability at Reduced Power / Low-Flow Condition (Catton).

- ABWR/APWR Passive Systems (Wylie)

- Use of PRA in the Regulatory Process (Kerr)

D.

Rymmarv/ List of Follow-up_ Matters (Open) o Owing to lack of time, the Committee was. not able to dtscuss and finalize the comments / recommendations provided by cognizant Subcommittee Chairmen / members on the following evolutionary LWR certification issues. The Committee plans to discuss these issues and a proposed ACRS report to the Commission on the evolutionary LWR certification ' issues during the April 5-7, 1990 ACRS meeting.

(Dr. El-Zeftawy has the follow-up action on this matter)':-

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359th ACRS Meeting Minutes 17 i

Evolutionary LWR Public Safety Goals Mid-Loop Operation Station Blackout Containment Performance Equipment Survivability Other Issues (to be identified by the Committee) o Mr.

Michelson proposed, and the Committee agreed, to discuss with the staff and gather additional information on fire protection provisions for evolutionary LWRs during the March 27, 1990 meeting of the Joint Extreme External Phenomena / Severe Accidents Subcommittees.

Mr. McCracken, NRR, agreed to provide the briefing on this matter.

(Mr.

Igne has the responsibility to make necessary arrangements for this briefing.)

o During the April 5-7, 1990 ACRS meeting, the Committee decided to hold discussions with the staff and gather additional inf ormation on the following evolutionary LWR certification issues.

(Dr. El-Zeftawy has the responsi-bility to make necessary arrangements for this briefing):

ABWR Containment Vent Design Equipment Survivability l

o Mr.

Michelson suggested that the-members review the comments / recommendations related to 10 evolutionary LWR cortification issues, that were discussed in detail by the l

Committee during this

meeting, with respect to the definition of "how safe is safe enough" included in the Commission's Safoty Goal Policy.

-(Dr. El-Zeftawy has the follow-up action on this matter.)

l t

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Dr.

Lewis requested that the members provide input

(

regarding additional issues, other than those identified l

by the staff in SECY-90-016, that they believe should be considered by tho staff for evolutionary LWRs..

(Mr.

Quittschreiber has the follow-up action on this matter.)

o Mr. Michelson requested that EPRI provide its optimization list that identifies safety issues related to evolutionary LWRs.

Representative of F?RI agreed'to provide this list.

(Dr. El*Zeftawy has the.vilow-up action on this matter.)

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359th ACRS Meeting Minutes 18 o

The Committee suggested that Dr. Catton, Chairman of the Safety Research Program Subcommittee, revise the proposed report on the NRC Safety Research Program budget and submit e

it to the full Committee for consideration during the April 5-7, 1990 ACRS meeting.

(Mr. Duraiswamy has the follow-

~

up action on this matter.)

Mr. Carroll suggested that the improved LWRs Subcommittee o

schedule a meeting as soon as possible to discuss with the staff, GE, Westinghouse, CE, and EPRI regarding passive plant designs.

(Subcommittee meeting has been scheduled for May 9, 1990 to discuss this matter.)

Mr. Fraley requested that the members identify additional o

items as soon as possible for discussion during the meeting between RSK and the ACRS scheduled to be held during June 1990.

(Mr.

Fraley has the follow-up action on thid matter.)

o Mr. Michelson suggested that during the June 1990 ACRS meeting the members discuss their technical papers that they plan to present during the meeting between the RSK and the ACRS.

(Mr. Fraley has the follow-up action on this matter.)

The Committee requested that the staff provide draf t copies o

of the technical reports associated with the CPI program that are being prepared by the staff's contractors.

Mr.

King, RES, agreed to provide copies of such reports.

(Mr.

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

o The Committee suggested that the staff reference the

report,

" Technical Aspects of Hydrogen Control and Combustion in Severe Light-Water Reactor Accidents,"

I prepared by the National Research Council in the proposed Supplement to Generic Letter 88-20.

Mr. King, RES, agreed to consider this suggestion.

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

The Committee agreed that during the April'~5-7, 1990'ACRS o

meeting, the NRR staff provide briefings to the Committee-on the following matters related to plant operations. (Mr.

Boennert has the follow-up action on this matter.)

NRR's efforts related to the development of emergency operating procedures f or the shutdown modes (Modes 3-

6) of operation.

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V 359th ACRS Meeting Minutes 19 r

Details of the technical violations surrounding the

$75,000 fine imposed by the staff on the Farley 4

nuclear plant.

Results of the Westinghouse owners' Group study in support of reduction of turbine stop valve testing frequency.

(Note:

This item has been deferred to the May 10-12, 1990 ACRS meeting.)

o The Committee suggested that the Regional Programs Subcommittee discuss with the Region II personnel the appropriateness of the $75,000 fine imposed by the NRC on the Brunswick Nuclear plant during one of the future meetings with Region II.

(Mr. Boehnert has the follow-up action on this matter.)

o Dr. Siess requested that his name be added to the list of members of the ACRS Subcommittee on Regional Programs.

(Dr. Siess' name has been added to this Subcommittee.)

o Drs. Shewmon and Catton requested copies of the reports on

" Bleed and Feed"/Depressurization prepared by-former ACRS member Mr. Reed.

(Mr. Boehnert has sent copies of these reports on March 14, 1990.)

o The Committee deferred consideration of the following to the May 10-12, 1990 ACRS meeting.

(Messrs. Boehnert, Igne, Quittschreiber, and Alderman have the follow-up actions on these matters):

Reactor Operating Events Interim Standard on Mot Particles Briefing on the Status of the Study related to decoupling of Siting and Source Term Nine Mile Point Unit 1 Restart AEOD Report on the Performance of Solenoid Valves l

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1 359th ACRS Meeting Minutes 20 2

E.

Future Activitie.E (Open) 1.

Future Acenda l

The Committee agreed to a tentative schedule for the April 5-7, 1990 ACRS meeting (Appendix II).

2.

Liture Subcominittee Activities i

A list of future ACRS Subcommittee meetings was distributed -

to members (Appendix III).

{

The meeting was adjourned at 12 15 p.m. on Saturday, March-10, 1990.

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I APPENDICES

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MINUTES OF THE-359TH ACRS MEETING

'[

MARCH 8-10,-1990

(

l 3

i I.

Attendees i

r II.

Future Agenda

't III.

Future Subcommittee Activities

. 1 IV.

Attachment:

AEOD Technical Review Report, TR Report No.

AEOD/T925, dated December 18,

1989,

Subject:

Evaluation-of Safety Equipment Outages for' Significance at Zion Presentation materials provided during the meeting.

e 3

REACTOR OPERATING EXPERIENCE e

Tentative Schedule Status Report with Briefing Slides:

e Point Beach Units - 1 &

2, 125 VDC System Circuit Breaker Design Problem, Nov.

7, 1989 Generic Issue (BWRs)

Potential LPCI Swing Bus Undervoltage Failure, Oct. 12, 1989 Robinson Unit 2 - Inadequate NPSH of Aux. Feedwater Pumps, Aug. 16, 1989 Presentation-materials provided during the meeting.

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4 CONTAINMENT PERFORMANCE IMPROVEMENT PROGRAM i

e Tentative Schedule Status Report with attachments:

o Memorandum for R.

Fraley from W. Minners,

Subject:

ACRS Review of Supplement 2 to Generic Letter 88-20, IPEs, dated Feb. 22, 1990 Draft Supplement No. 2 to Generic Letter 88-20 re CPI Program and Insights for IPE Draft SECY-90-XX, Recommendations of CPI' Program for Plants with Mark II, Mark III, Ice Condenser and Dry j

Containments (INTERNAL COMMITTEE USE ONLY)..

Appendix 1 to Generic Letter 88-20, Guidance'on the Examination of Containment System Performance (Back-End Analysis), Nov. 23, 1988 Supplement.No. 1 to Generic Letter-88-20, Mark I CPIs, Aug. 29, 1989 Generic Letter 89-16, Installation of a Hardened Wet well Vent,. Sept.

1, 1989

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359th ACRS Meeting Minutes Appendix IV-2 L

Tith 4 (Continued)

Abstract and Executive Summary from NUREG/CR-5275, FLAME Facility, April 1989 Reference Article from ANS Proceedings.

HECTR I

Assessment of Some HDR Experiments,. August 1989 5.1 List of Future ACRS Subcommittee Meetings-5.2 Future ACRS Activities 6

EVOLUTIONARY LIGHT WATER REACTOR CERTIFICATION ISSUES Tentative Agenda l

o e

Status Report with Attachments:

SECY-90-016,

" Evolutionary Light Water Att.

I Reactor (LWR)

Certification Issues and Their Relationship to Current Regulatory Requirements,"

R dated Jan. 12, 1990 i

Att. II - Memorandum from S. Chilk, Secretary, for J. Taylor, EDO and C. Michelson, ACRS, Re:

Staf f Requirements - SECY-89-334 Recommended Priori-ties for Review of Standard-Plant Designs," dated Dec. 15, 1989 Att. III - Memorandum from S. Chilk, Secretary, for J. Taylor, EDO, and C. Michelson, ACRS,-Re:

" Staff Requirements - SECY-89-311 --Resolution Process for Severe Accident Issues on Evolutionary Light Water p

Reactors," dated Dec. 15, 1989 Att. IV - Memorandum from R.-Fraley, ACRS to ACRS Members, Re:

Certification Issues for Evolutionary t

LWRs, dated March 1, 1990.

HANDOUTS 2-1 Report AEOD/5902, dated March 1990:

Special Study Report, Review of Thermal Stratification Operating Experience.

4-1 ACRS -_ Consultant Michael L.

Corradini-Report to David Ward,.

Subcommittee Chairman, on ACRS Containment System Subcommittee February 6,

1990 Meeting, dated Feb.

8, 1990 (INTERNAL COMMITTEE USE ONLY).

6-1 EVOLUTIONARY LWR CERTIFICATION-ISSUES Memorandum for ACRS Members' dated March 5, 1990 from H.

S.

Schofer, ACRS,

SUBJECT:

CERTIFICATION ISSUES FOR EVOLUTIONARY -

LWRs.

,

ML20062C648

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