ML19260B463
| ML19260B463 | |
| Person / Time | |
|---|---|
| Issue date: | 10/17/1979 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-1660, NUDOCS 7912100204 | |
| Download: ML19260B463 (11) | |
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MINtfrES OF THE ACRS SUBC04MITTEE ON adNANCED REACTORS E
Wh58INGTON, D.C.
JULY ll, 1979 The ACRS Subcommittee on Advanced Reactors held an open meeting on July 11, 1979 in Room 1162, 1717 H Street, N.W., Washington, D.C.
Se purpose of this meeting was to review matters related to the ACRS review of the NRC Notice of this meeting was pub-sponsored research on advanced reactors.
lished la the Federal Register on June 26, 1979. A copy of this meeting is included as Attachment A.
A list of the attendees for this meetirg is included as Atte.chment B and a schedule for this meeting is incitxied as Attachment C.
Selected portions of the meeting handouts are included as Attachment D.
A complete set of handouts has been included in the ACRS files. No written statements or requests to give oral statements were re-ceived from menbers of the public. W e meeting was attended by Dr. W. Kerr, Subcommittee Chairman, and Dr. J. C. Mark, Subcommittee member and Dr. T. G.
McCreless of the ACRS Staff. he meeting was opened at 8:30 am with a short Executive Session during which Dr. Kerr summarized the schedule and the goals for the day's meeting. Se meeting was held entirely in open session and was adjourned at 12:00 noon on this day. W e designated Federal Employee for this meeting was Dr. T. G. McCreless.
RES/ARSR BUDGET AND ACTIONS ON ACRS RECOMMENDATIONS-C. KELBER, NRC/RES Dr. Kelber summarized the current advanced reactor budget. We FY 79 bud-get was $12.5M for fast breeder reactors and $2.9M for advanced converter We approved FY 80 spending was $13.7M for fast breeder reactors reactors.
and S0 for advanced converter reactors.
(The office request for FY 80 was for $15M for fast breeder reactors and $3.7M for gas reactors.) The office request for the FY 81 budget is $22.lM for fast breeder reactors and S3.9M he BRG has reviewed the office request and for fast converter reactors.
has referred the matter to the Commissioners as a " set aside" item to be decided on the basis of whether or not the NRC should support research on advanced reactors considering the present prospects for a near term appli-cation for a license. Se BRG additionally recanmended that the progran 2124 339 7912100 A D
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_. -mm Advanced Reactors July 11, 1979 either be supportd at the requested level or not at all. Requested levels for FY 82 and FY 83 are $31.6M and $38M for fast breeder reactors, and SlCM and S13M for advanced converter reactors.
Dr. Kelber briefly discussed the relationship of the RSR sponsored research to the DOE lines of assurance (LOA 1,2,3,4). Wis is strnmarized on Figure 1 of Attachment D.
Dr. Kelber indicated that it was his belief that re-search on advanced reactors must be done now if the Commission is to be prepared for future license applications.
Dr. Kelber addressed the ARSR actions on the ACRS recommendations. A stramary is given on pages 2 through 4 of Attachment D.
Dr. Kelber discussed the proposed FY 81 budget increases. We analysis work is budgeted for SS.4M for FY 80 and S7.8M is being requested for FY 81.
Se increment will be used to complete and issue the accident analysis codes currently under development. Se Safety Test Facilities studies will be inactive in FY 80 and have a proposed funding of S.7M in FY 81. Eis funding will be used to reactivate the FY 78 ARSR progre on the Safety Test Facilities studies. We Materials Interaction area is budgeted for
$2.8M in FY 80 and has a requested budget of $3.0M for FY 81. He addi-tional funding will be used to initiate new core melt aerosol source and transport work. We System Integrity program is budgeted for $3.3M in FY 80 and has a requested level of $6M in FY 81. He additional funding will be used for the qualification of the CONTAIN code and large core melt re-tention tests.
Se goals and the requested funding level for the FY 81 prograa would be as follows:
- 1) Analysis area (a)
Issue the CONTAIN, BIFLO, and SSC-S codes (b)
Complete the tw-phase CCMMIX-2 and BODYFIT codes (c) Complete Phase 2 of the accident delineation sttriies (d) Continue the code qualifications prograns 2124 340
July 11, 1979 Advanced Reactors Safety Test Facilities studies (to reactivate the progra=s which were 2) terminated after FY 78)
- 3). Materials Interaction area (a) To design and f abricate a sodium loop for the ACRR (b)
Io perform accident seven pin energetics capsule tests in the ACRR To perform fuel dispersal tests with radiated fuel in the ACRR (c)
(d) To conduct transition phase tests in the ACRR
- 4) Aerosol Release and Transport area To extend the capabilities of the HAARM-3 code to core melt (a)
To conduct the HCDA source terms with sodium in the FAST (b) facility (c) To expand the core melt aerosol source term test program and test in the NSPP.
to conduct core melt aerosol transport
- 5) Systems Integrity area To continue the qualification process for the CONTAIN code (a)
(b) To conduct large core melt retention tests core debirs coolability tests in the ACRR (c) To conduct loads To conduct cell liner response tests to accident (c)
The 53.9M requested for the Advanced Converter, the FY 81 budget will continue the program which was underway in FY 78.
SUMMARY
OF THE A'?ALYSIS AREA-R. CURTIS, NRC/RES The Dr. Curtis su=marized the ARSR sponsored research in the analysis area.
and verification of bulk of the funding is being spent on the development The SIEMER, CONTAIN, SSC, and COMMIX /BODYFIT codes are the computer codes.
most important areas of effort.
Dr. Curtis indicated that these codes will the results of experiments and to examine bee used to analyze and extrapolate The most heavily funded the safety characteristics of conceptual designs.
and verification and the SSC areas currently are the SIMMER code development code development and verification work.
2124 34;
Advanced Reactors July 11, 1979 EXPERIMENTAL WORK - M. SILVERBERG, NRC/RES Dr. Silverberg summarized the ARSR sponsored work in the experimental area.
The upgrading of the ACRR was completed during FY 79 and the test program has been initiated in the upgraded facility. The pulse level and the steady state flux capability have been increased more than the factor of 3 by this upgrading. The coded aperture imaging system has been installed. This equip-ment will be used to study fuel motion in in-pile tests. The upgraded reactor should have the capability to perform reasonably prototypical experiments with up to 7 pins. Funds for the design and fabrication of a flowing sodium loop for ACRR have been requested for FY 81.
Dr. Silverberg noted that the ACRR work will address the current uncertainties with regard to fuel coolant inter-action. Extended core debris cooling experiments will be perfor=ed in the upgraded ACPR. The current ARSR core melt technology program has for..ed on the core melt interactions with concrete.
In FY 79 a program in which alter-4 nate materials to concrete are treated has been initiated. This program will continue.
Dr. Silverberg noted that this work is of =uch interest in the FNP application. The aerosol release and transport programs in the FAST and NSPF facilities are proceeding through the planned experimental matrix.
ADVANCED CONVERTER REACTOR PROGRAM - R. FOUL.DS, NRC/RES/ARSR Mr. Foulds su==arized the ARSR sponsored work in this area. He noted that the funding for FY 80 has been eliminated and the program is currently directed towards the orderly termination of this work. There is, however, some possi-bility of funds being redirected back into the program in FY 80.
The termination of the program was related to a desire to suspend NRC research until direction of theD0e development program becomes more certain. The budget research for FY 81 calls for a funding level of $3.9M which will support a minimal level program in this area.
It is expected that the directions of the DOE program will be more certain at that time.
The meeting was adjourned at 12:00 noon on this day.
2124 342
I Federal Register / Vol. 44. No.124 / Tuesday, June 28, 1979 / Notices 373S1 NW (between H St. and Pennsylvania
[
ket No. 50-3631 -
action, see (1) Amendment No.12 to Ave.). Washington. DC 20535 to continue
-d Facility Operating Ucense No.NpF-8 its review of natters related to the NRC ansas Power and ught Co.
and (2) the Commission's related Safety sponsored research on the safety of (Ankansas Nuclear One Unit 2);
Evaluation supporting Amendment No.
advanced reactor designs.
Isshance of Amendment to Faci!!ty 12 to I.icense No. NPF-6. These items In accordance with the procedures Op ating Ucense are available for public inspection at the out!!ned in the Federal Register on Th,U.S. Nuclear Regulatory
- i8sion s Publi D R
Cctober 4.1978 (43 FR 45928), oral or Co ssion (the Commission) has H S,g D.C wntten statements may be presented by issued endment No.12 to Faci!Ity 20555 and the Ark'ansas Polytechnic members of the public, recordiigs will Operat g cense No. NFF-4 t College. Russellville. Arkansas 72801. A be permitted only during those portions Arkans s Po e and I.ight Company for copy ofitems (1) and (2) may be obtained upon request irddressed to the of the meeting when a transcript is being p] rat, U.S. Nuclear Regulatery Cornmission, ansas ea e,
kept and questions may be asked only by members of the Subcommittee.its ns e s ite m.
Co, Washington. D.C. 20155. Attention:
3, g, Director. Division of Project consultants, and Strff. Persons desiring to maxe oral statements should notify effective as fits date c 'ssuance.
Management. Of5ce of Nuclear Reactor Regulation.
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na a e s p acu ab so that a ty a
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de Mad h M hy appropnate arrangements can be made y mo g e re ot to a!!aw the necessary time during the o{t te ch ge on the John F. Stolz.
meeting for such statements.
core protection alculator syste ased c'nef. Lght Water /teacrees Brench No. I The agenda for subject meeting shall on Coremission pproval of the Ui'18 ion o/holec Managen ent.
y be as icilows:
licensee's chang procedures. Also, e
- rn omsm rw ws-m W Technical Specifi tions have been ewo coes isome Wednesday July 11,1979 changed to includ a Nuclear Software E.xpert as a membe of the licensee's j
820 a.m. untilthe conclusion of Plant Safety Cocuni ee. Finally, the
- "**
- 20 busmess amendment removes nother condition ne Subcommittee may meet in regarding implementa ion of redundant silability of Environmental Report Executive Session, with any ofits valve position mdicati n m the control
'and Intent to prepare a Draf t consultants who may be present, to to m which has been v nfied to be
/Enytronmentalimpact Statement ConStrning issuance of a Source explore and exchange their prelimmary completed m accordanc with design Maten3rLUcense To Rocky Mountain opmions re8arding matters which should m dificat:ons previously approved bY the Commission.
Energy Cget al be considered dunng de meeting and t Acaxcw U.S. Nuclear Regulatory formulate a report and The Commission has m de reco.nmendat2ons to the full Committee. appropriate findings as req \\: ired by/he Commission. Division of Waste At the conclusion of the Executive Atomic Energy Act of1954.hs amghded Management (the Act) and the Com=issi
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AcnoN: Notice ofIntent to Prepare a Session. the Subcommittee will hear regulations in to CFR Chapte !. 4vhicli Draft Environmental Impact Statement.
presentations by and hold discussions are set forth in de amended li nse. We with representatives of the NRC Staff, have concluded that becausef. e sumn 1. Description of the Proposed and their consultants, pertinent to the amendment does not involve Action-Rocky Mountain Energy above topics.The Subcomnuttee may significant increase in the ba 'lityor Company (RMEC), in partnership with then caucus to determine whether the consequences of accidents revia sly Mn Power Company and the matters identified in the initial session considered and does not i olve a Halliburton Company, propose to have been adequately covered and significant decrease in a fety =argin, p'
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whether the project is ready for review the amendment does no volve a y,
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d by the full Committee.
sigmEcant hazards con deration. Th
C I
- [i d b's Further information regarding topics application for the lic se amendment y
to be discussed, whether the meeting complies with the sta dards and Mile !ake. The ;.oposed project area is, has been cancelled or rescheduled. the requirements of the cf and the appr9ximately 14.5 km (9 miles) north of Cas m.
Chairman's ruling on requests for the Cormnission s r
'ons.
gy g,
gg opportunity to present oral statements The Commission, as determine'd dat and the time allotted therefore can be the issuance of thi4 amendment will not mended. requires persons who " receive obramed by a prepaid telephone call to result in any sign /icant environmental
- t. e to, receive, possess, use transfer, the Designated Federal Employee for impact and that fursuant to 10 CFR d 'iver,., any source =atenal.
(i.eg uranium end/or thonum in any dis meeting. Dr. Thomas G. McCreless Section 51.5(d)(f) an environmental fa..
.) to obtam a Source Matenal (telephone 202/634-3257) between S;15 impact statement er negative I.icen e. Title 10 of de Code of Federal a.m. and 5.00 p.m. EST.
declaration and environmentalimpact Regulhions. Psrt 51, provides for the w jun, 2,.g g, appraisal need not be prepared :n gg connection Mith issuance of Sis preparation of a detailed environmental statenleh! pursuant to the National Advisory Camtmtr.ee Management CTicer.
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ACRS ADVANCED REACTCRS SUSCOMMITTEE MEETING JULY 11, 1979 WASHINGTON, D. C.
ATTENDEES LIST ACRS NRC G rent, Chairman L. Shao, RES/ARSR P. Shewman, Member J. Richardson, RES/GRSR M. Sender, Member G. Bagchi, RES/GRSR H. Etherington, Member J. Harbour D. Moeller, Member C. Siess, Member E. Igne, ACRS Staff
- R. Savio, ACRS Staff *
- Designated Federal Employees MISCELLANEOUS
- 0. Hoffman, Ace Federal F. D. Linzer, Westinghouse ARD A. Sosenig, McGraw-Hill J. Graham, Gemeral Atomic J. McInerney, Westinghouse D. W. Dixon, SCE & G Co.
W. A. Williams, Jr., WSC Public Service Authority 2124 344
Tentative Schedule Advanced Reactors Subcomittee July 11, 1979 8:30 - 8:45 Executive Session 8:45 - 9:15 Overview of Programs
-Changes and accomplishments in FY 79 and future plans.
9:15 - 9:30 Actions on ACRS Recommendations (REF: Chapter 6 of 1979 Report to the Congress).
9:30 - 11:30 General Discussion 2124 345
PROGRAM BALANCE o
ADVANCED REACTOR SAFETV RESEARCH E
W ACCIDENT CONTAINMENT, MITIGATION C"3 M
FY 70:
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CON T AltJ SOOlUM COtJ T AINMENT MOLILN COllE ltJIEll ACTIONS AEllOSOL litt L ASE AND Ill ANSPOlli IlIVE PliOJLCIS) s "4
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/ StJPLit SYSi t M CODE LLI VAILO ILtJPLitAluitE DESIGN ASSESSMENT CitLLP I AI GUL INit ilACilON Str.1 Melt ',
j ACCIDENI ENt:ltGC f fCS Sill AltJ lt Ar!GL' PAlllillOfJif4G N
p TillitMollYDilAULICS OF L Millit ACCIDENIS '
til AM CAllill/ ACilli CO(,PE It A I lON EVf NI 184LIS
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CORE u ACCIDENT MELT A INITIATION, ACCIDENTS l'ilEVENTION FY 70:
FY 70:
$2,000.000
$5,700,000 A
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ACRS RECOMMENDATIONS - ARSR PROGRAM 01UREG-Oli96) flEC0lil5EllDALIO((
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COMPREllENSIVE STilDY OF SAFETY ISSUES FOR 0 [VDIT IREE PROGRNi DEVELDPS CADRE COMr1ERCI AL LMfllR--USE PRODABILISTIC FOR STlIN OF ITES - DE EFF0nr (1981).
AtlALYSIS TECilillallES
- CooecRATIVE STUDIES Willi (K.
- Joitir FUEL 1ESTS WIllt fl6.
8 INITI ATE SCOPillG STUDIES Ott GCRS SIMILAR 0
FUflDING NOT AVAILABLE.
TO LHFBRS (DIRECT CYCLE llIGR & GCFR).
e lillTI ATE STUDIES WillCil PLACE EMPilASIS e
UK-USNRC ACCIDENT INITI ATI0tt STUDIES.
ON CDA PREVEllTION.
o ADDED WORK TO FOLLOW EVENT TREE STUDY.
O INFORMATI0ll MEETINGS lllTil DOE & CONTRACTORS (NExT ME.
iNG Ort LOA-1, 7/11 8 12).
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ACRS RECOMMENDATIONS - ARSR PROGRAM (NUREG-0'196)
COMEfH.
RECOMMEllDAIl0H.
S USE CONTAlli CODE, STRUCTURAL INTEGRITY e
STUDY PRO AtlD COIL 0F Al_TERilATE CONTAINMENT DE S I GilS (E i.G., FILTERED 8 VEitTED DESIGNS).
TESTS AllD ART PROGRAM TO DEFINE CONTAIllMENT TIIREAT.
REACTIVATE SIf STUDIES AllD USE SSC O
DETERMINE HilETilER flEH EXPERIMEtlTAL FACILITIES 0
C0t1 MIX.
OR PROGRAlls ARE ilEEDED TO DEMONSTRATE VALIDITY OF NATURAL CONVECT 10ft C00LillG FOR C0tV1ERCIAL-SIZED LMFBRS (POOL AND LOOP TYPES).
EVALUATE Oil CollTilluf flG DASIS flEED FOR NEhe REACTIVATE SIF STUDIES.
o LARGE-SCALE EXPERIMENTAL APPARATUS.
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ACRS REC 0fEEllDAT10lls - ARSR PROGRAM (flVREG-Ofl96)
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RECOMMEllDAUDft 8
APPROXIMATELY ll0% OF TifE BUDGET DEVOTED C0llTitlUED STUDY OF Tile CDA AtlD Tile TO SUPPORT WORK Ill Tills AREA.
IllE e
RESOLUTiell UF PROBLEMS ASSOCI ATED WITil SIMMER CODE AllD ACRR TESTS MAKE MAJOR IT, E.G.,
POST-ACCIDEllT llEAT REMOVAL.
CollTRIBUT10tlS.
O GREATER EMPilASIS DE.PLACED Oil DEVELOPillG e
SPECIFIC COLLA:10RATI6tlS lti PROGRESS UllDER E.XISTillG EXCllAt1GE AGREEMEllTS A PLAllilED, MElll0 DICAL Pil0 GRAM TO KEEP WITil FRG,.lAPAll, UK & CEA-KFK ABREAST AtlD PROBIT FROM SAFETY RESEARCil (CAllRl); 8!t0AD AGREEMEllT WITil PEllFORMED Ill 0 tiler flATI0tlS.
CEA (LATE 1979) WILL PERMIT FULL EXCil AtlGE titill IllT'L LEADERS lit f UR IEClit10 LOGY, N
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