ML20205D399
| ML20205D399 | |
| Person / Time | |
|---|---|
| Issue date: | 03/06/1987 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2484, NUDOCS 8703300396 | |
| Download: ML20205D399 (19) | |
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DATE ISSUED:3/6/87 COMBINED
SUMMARY
/ MINUTES OF THE JANUARY 7, 1987 MEETING OF THE ACRS SUBCOMMITTEE ON GENERAL ELECTRIC REACTOR PLANTS WASHINGTON, D. C.
A meeting was held by the ACRS Subcommittee on General Electric Reactor Plants on January 7, 1987. This was the morning half of a joint subcom-mittee meeting on General Electric Reactor Plants and Safety Philosophy, Technology and Criteria.
The purpose of this half of the meeting was for the General Electric Reactor Plants Subcommittee to begin its review of the General Electric Advanced Boiling Water Reactor (ABWR). This was a preliminary session to explore the status of this project ano to be briefed on efforts regarding a licensing basis agreement (LBA) betwaen GE and the NRC Staff. A current description of the ABWR was sought as well as schedules from GE and the Staff.
(The a#ternoon Safety Philosophy, Technology, and Criteria session reviewed the status of the NRC Staff's work on the Safety Goal Policy, on USI A-17, " Systems Interactions on Nuclear Power Plants", and on Steam Generator Overfill.)
5
.og a-Notice of this meeting was published in the Federal Register on December O
S 23 and 29, 1986 (Attachments A). Attachments B are tentative schedules
$tn for presentations and Attachment C is a list of slides and tendouts on o5 g<
file in the ACRS office. The meeting (morning session) was entirely n e RE@
open to the public. Richard Major was the cognizant ACRS Sta'f Member cn a.rd for this meeting. The meeting began at 9:00 a.m.
C.
IN O
DESIGNATED ORIGINAL M
Certified By l
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.c Minutes /GE Meating 2
January 7, 1987 i
k Attendees ACRS General Electric Company D. Okrent, Chairman C. Sawyer D. Wilkins C. Michelson, Member, R. Villa M. Carbon, Member L. Gifford F. Remick, Member R. Ketchel C. Siess, Member L. Neal J. Ebersole, Member D. Ward, Member C. Wylie, Member NRC Staff R. Major, ACRS Staff W. Butler C. Sun, ACRS Fellow R. Hernan T. King Others S. Black J. Guppy, BNL R. Caruso A. Omoto, Tokyo Electric Power Co.
F. Ross, DOE F. Stetson, NUS Corp.
M. Beaumont, Westinghouse J. Berga, EPRI G. Brown, Stone & Webster R. Schaffstall, KMC, Inc.
- 0. Williams, J/R/A J. Trotter, NMS L. Connor, DSA D. Hoffman, ACR Federal Peporters 1.
Dr. Okrent brought the meeting to order at 9:00 a.m. and reviewed the purpose of the meeting. He noted special attention should be focused on what the licensing basis agreement does and does not contain.
2.
Mr. Ebersole noted he wanted to hear arguments why an Ultimate Plant Protection System was not included in the ABWR, He noted a lack in addressing A-45, Decay Heat Removal. He also felt improvements were in order for the semiautomatic release system. More thought was also recomended on diverse water supplies for ECSS and molten core action on the containment floor, r
Minut:s/GE Mesting 3
January 7, 1987
'r '
3.
Mr. D. Wilkins of General Electric presented an overview of the ABWR program. The objectives of the ABWR program are to improve the operability, capacity factor, safety, and overall performance of the BWR while reducing occupational exposure, reducing radioactive waste, and reducing all elements of plant cost.
4.
Mr. Wilkens explained the ABWR was begun using an international team of 25 engineers.
Between 1978 and 1979 the ABWR concept was created.
The design development and confirmatory testing has been primarily focused in Japan. GE, Hitachi, and Toshiba have led the technical effort with support from Tokyo Electric Power Co. and a consortium of Japanese utilities. At this point, testing of new fea-tures on the ABWR are essentially complete.
To date, on the order of
$250 million has been invested in this program; the ABWR is ready for lead plant application. Currently the first plants are expected to be built in Japan in the early 90's and will be in operation by the mid-90's.
5.
ABWR performance characteristics were reviewed. The electrical output is 1350 MWe. The plant is engineered for a construction schedule of 48 months. The capacity factor is expected to be 86%.
Refueling and Maintenance outages are expected to be 55 days per year. A core damage probability of less than 10 E-6/ year is estimated.
6.
The U.S. ABWR program has as its objective to obtain NRC Certifica-tion of an Advanced BWR for use by multiple utilities on multiple sites.
GE hopes to complete this effort by 1991. The approach GE hopes to take
Minutes /GE Metting 4
January 7, 1987 GI will include using the EPRI advanced LWR requirements document, providing a design consistent with these requirements, and obtaining DOE /NRC regulatory certification.
7.
A key element in the ABWR review will be a licensing basis agree-ment (LBA). The LBA will be an attempt to define the important require-ments that must be covered during the ABWR review. GE hopes to set the ground rules for the review using the LRA by the middle of 1987.
8.
Dr. C. Sawyer, GE, covered the ABWR design features and the status of research and development efforts. He noted the ABWR incorporates the best worldwide BWR features which include:
internal recirculation pumps, fine motion control rod drives, digital / solid state control, multiplexing, advanced fuel, improved containment and reactor building, and three ECCS divisions.
9.
The ABWR reactor vessel uses internal recirculation pumps. Ten internal pumps are bottom-mounted around the periphery of the vessel.
They are of a wet motor type.
Full core flow can be achieved with one 1
pump out of service. The vessel itself is supported by a conical skirt from the side.
It was explained that the use of internal recirculation pumps eliminates the external recirculation piping, thus eliminating a large source of occupational exposure and recent pipe-cracking diffi-culties. The ABWR design also eliminates large nozzles on the vessel below the core.
Minutes /GE Meeting 5
January 7, 1987 W
- 10.. The fine motion control rod drive system uses hydraulics for scram, and electric motors for normal plant activity rod motion. The electric system does back up the hydraulic system, should the hydraulic scram fail. The scram discharge volume has been eliminated. Water used to drive the rods into the core enters the reactor vessel itself. The electric drive can step in increments of 3/4 of an inch as opposed to the present six inches per step.
- 11. Advanced fuel will be used in the ABWR. The fuel uses a barrier design capable of high exposure. The fuel uses axially zoned enrichment and gadolinia to flatten the axial power shape without the use of rods.
- 12. The emergency core cooling system (ECCS) of the ABWR uses three di-visions with both a high and low pressure ECCS in each zone. Each division is separated both mechanically and electrically.
- 13. The ABWR employs a digital / solid state control system. The system is fault-tolerant and triple redundant. The system also uses self diagnostics. This new technology represents a cost saving. The control system uses multiplexing and has fiber-optic isolation capability.
- 14. The ABWR has an improved containment and reactor building. The containment is a lined reinforced cylindrical concrete building. The suppression pool is similar to that found in a Mark III containment with horizontal vents. The pool is covered and the containment inerted. The reactor building is integrated with the containment.
It is a smaller volume than a Mark III, but with improved seismic capability.
Minutes /GE Meating 6
January 7, 1987 9
- 15. The ABWR test and development program has as its philosophy the concept that every feature of this design had to be either proven by operating experience or proven by a test program. There are on the order of twenty major test programs.
- 16. Mr. Villa, G.E., discussed the licensing basis agreement being requested by General Electric.
It was stated that the purpose of the LBA is to define those issues that must be addressed during the technical review of the ABWR. The LBA is intended to establish an acceptable process for the certification of the ABWR design. This is an effort to stabilize the licensing process.
It should also define a process for making future changes. GE also hopes the LBA will define the inner-relationship between the ABWR project and the EPRI Advanced Light Water Reactor Program. Mr. Villa expressed a desire to obtain the Committee's connents on the idea of a licensing basis agreement.
- 17. Mr. Villa discussed schedules for completing the LBA. Currently, GE would like to have the LBA approved in June of 1987 and begin the technical review of the ABWR in September 1987.
- 18. Ralph Caruso, Senior Staff Project Manager, presented highlights of the Staff ABWR licensing program.
He noted that the ABWR project involves new concepts in licensing including: a new standardized BWR design, the use of the licensing basis agreement, the design certifica-tion process, and the use of the EPRI light water reactors requirements document. Since a lead plant may first be built in Japan, coordination
Minutes /GE Metting 7
January 7, 1987 b
on the review effort between U.S. and Japanese regulatory agencies is anticipated.
I
- 19. Mr. Caruso explained that topics to be included in the LBA will include technical issues, how the tool of probabilistic risk assessment (PRA) is used, the treatment of the severe accident policy statement, and the EPRI ALWR program.
In some cases, the details of these compo-nents (the use of PRA and the severe accident policy) are still evolv-ing. Other potential topics to be included in the LBA include:
the scheduling of review, review procedures, site specific issues, orga-nization, and design completeness and degree of detail.
The Staff is currently scheduling the completion of the final design approval review in 1990, and completing the certification process by 1991.
- 20. Mr. Caruso noted the LBA has no basis in the regulations and is not legally binding, it is a reasoned expression of intent by the Staff and the Applicant. The Staff does not consider the backfit regulation applicable to the ABWR review until after the final design approved has been issued.
New issues that arise during the review will be treated according to procedures outlined in the EPRI program and contained in Section 8.2 of the draft LBA. The LBA will be issued as a NUREG document.
- 21. A question and answer session was held on the design details of the G.E. Japanese ABWR,
Minut:s/GE Meeting 8
January 7, 1987 p
o GE commented on their position regarding the use of contain-ment filtered vents. Their philosophy is that fission prod-ucts caused by a accident should be held within the contain-ment. A deliberately engineered breach in containment is not favored.
The probability of a containment failure is felt to be low enough so that a procedure to bypass the containment is not needed.
It was also noted that the suppression pool does have filtering capabilities, o
GE did note that a containment penetration which can accomo-date a filtered vent has been left in the design. There will be no filtered vent in the Japanese ABWP..
- 22. General Electric explained that they are proposing ABWR as a nuclear island concept, not an entire balance of plant.
Interface requirements that account for the portion of the plant outside of the ABWR scope will be provided. The amount of design detail that will be provided will be consistent with t.he A.I.F.'s recommendations.
It was noted a scale model of the ABWR design exists in Japan. This model represents pipe sizes down to several inches in diameter.
23.
In response to questions from Dr. Okrent, GE explained the LBA is an attempt to resolve problems that are currently identified and to set up a procedure to deal with issues that have yet to be discovered.
In areas where the licensing basis agreement is silent, it reflects the fact that a particular issue has not been addressed in the review. Such issues would not require a backfit finding to be addressed. New issues
Minut:s/GE Meeting 9
January 7, 1987 N'
will be addressed according to procedures developed in the EPRI ALWR Utility Requirements Document.
- 24. Dr. Okrent gave GE and the Staff instructions for presentations to be made to the full ACRS on the following day.
The morning session was recessed at 1:10 p.m.
NOTE:
A transcript of the meeting is available in the NRC Public Document Room; 1717 H Street, NW, Washington, DC or can be purchased from ACE-Federal Reporters, 444 N. Capitol Street, Washington, DC 20001 (202) 347-3700 r
A-I I
TENTATIVE SCHEDULE FOR THE JOINT ACRS SUBCOMMITTEE MEETING 0F THE
'p GENERAL ELECTRIC REACTORS (ABWR) AND E 24 W SAFETY PHILOSOPHY, TECHNOLOGY, AND CRITERIA SUBCOM ITTEES JANUARY 7, 1987 1717 H STREET, NW, ROOM 1046, WASHINGTON, DC
+
9:00 a.m.
1.
Chairman's Introduction, D. Okrent (10 Min.)
9:10 a.m.
2.
Licensing Basis Agreement (1hr.20 Min.)
(GE/NRC Staff)
A. General Description what was requested
- what seems practical
- areas covered / areas excluded B. Current Time Table 10:30 a.m.
BREAK (10 Min.)
10:40 a.m.
3.
(Ihr.40 Min.)
A. Overall description B. Description of Special Design Features as appropriate, including:
- Containment Capability given a Core Melt *
- Fire Protection *
- Protection Against External Attack *
- Dedicated Systems *
- Filtered Vents for Containment *
- Design Features to Protect Ground Water Given a Severe Accident *
- What is the Safety Goal Sought by G.E.
- Seismic Design Basis / Risk
- Methods for Improved Maintenance and Self Testing *
- Automation of Controls
- C. Comparison with GESSAR II D. Current Operating Experience with Advanced Designs 12:20 p.m.
4.
ABWR Review Schedule (NRC)
(30 Min.)
A. U.S. Schedule
- Interaction with EPRI B. Japanese Schedule
- Staff interaction with Japanese regulators The ACRS is currently considering recomendations for future light water reactors that may include these topics. General Electric is requested to discuss how they would deal with recomendations for improvements in these areas.
B
?
l are u ass 12:50 p.m.
5.
Future ACRS Activities
- 321st ACRS Meeting, Jan. 8-10, 1987 (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> scheduled) 1:00 p.m.
LUNCH (1hr.)
2:00 p.m.
6.
Executive Session, D. Okrent (15 Min.)
2:15 p.m.
7.
Discussion of the NRC Work on the Development of the Commission Safety Goal Policy A. Sumary of NRC Staff and Comission (15 Min.)
actions, schedules and proposed ACRS actions B. Discussion of the proposed framework (90 Min.)
for Safety Goal Policy implementation C. ACRS coments and general discussion (30 Min.)
D. Okrent D. Sumary, conclusions and future (15 Min.)
ACRS actions - D. Okrent 4:45 p.m.
BREAK (15 Min.)
5:00 p.m.
8.
Discussions on USI A-17 " Systems Interaction in Nuclear Power Plants" A. Sumary of NRR actions on developing (15 Min.)
a resolution for USI A-17 since May l
1986 - N. Anderson.D. Thatcher l
B. Discussion of NRR response to ACRS (30 Min.)
recommendations Ref. May 13, 1986 ACRS ltr.) - D. Okrent/N. Anderson and D. Thatcher C.
Sumary, conclusions, and future (15 Min.)
ACRS actions - D. Okrent 6:00 p.m.
9.
ACRS coments on the status of the NRC (15 Min.)
l plans for the resolution of steam generator overfill i
1, t
b MC24 W NRC Staff will supply a written report by Dec. 30, 1986 which will:
i
- describe the NRC current Task Action Plan for the completion of this work 4
- describe what the NRC Staff has done to respond to ACRS coments
- give a status report on the progress of the technical work 6:15 p.m.
ADJOURN i
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4 i
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A-L 4
1 J
GENERAL $ ELECTRIC NUCLEAR ENEAGY IUSINESS OPutATIONS GENERAL ELECTRIC COMPANY e 175 CURTNER AWNUE e SAN JOSE, CAUFCANLA 95125 December 19,1986 Dr. David Okrent, Chairman ACRS Subcomittees' on General Electric Reactors (ABWR) and Safety Philosophy, Technology, and Criteria 439 Veteran Avenue Los Angeles, CA 90024
Dear Dr. Okrent:
Thank you for your support of the ACRS Subcomittee meeting to discuss the General Electric Advanced Boiling Water Reactor (ABWR) January 7, 1987.
We believe the ABWR has some unique features which enhance the safety of the boiling water reactor.
The ABWR design has been developed over a period of 8 years and is now ready to be licensed through the support of the DOE Verification Program.
The program recognizes the EPRI-ALWR Requirements Program and agreements have been worked out with that program for the clear understanding of issue resolution.
In keeping with the intent of EPRI-ALWR Requirements Program, and within the schedule of licensing activities planned for the ABWR, we propose the attached agenda for your consideration at the January 7 meeting.
Such an agenda would provide the Subcomittee with a beneficial understanding of the working relationship of the ABWR Program with other programs as well as provide adequate coverage of the agenda items of your memorandum, dated December 17, 1986.
We will call you to confirm this agenda.
We look forward to meeting with you and your committee on January 7.
Sincerely,
~
Ricardo Artigas, Manager Licensing and Consulting Services
l cc: Richard Major, ACRS Frank Ross, DOE Dan Noble, EPRI Ralph Caruso, NRQ
.-y.,
.o PROPOSED AGENDA FOR THE JOINT ACRS SUBCOMMITTEE MEETING OF THE GENERAL ELECTRIC REACTORS (ABWR) AND SAFETY PHILOSOPHY, TECHNOLOGY, AND CRITERIA SUBCOMMITTEES January 7, 1987 1717 H Street, NW, Room 1046, Washington, DC 9:00 a.m.
Chairman's Introduction D. Okrant 9:10 a.m.
ABWR Program Overview Obj ectives Development Approach U.S. Licensing Certification Plan Relation to EPRI-ALWR Program Current Status 10:00 a.m.
ABWR Design Description Reactor systems including reactor internal pumps and fine motion control rod drives Plant perforstance Safety systems Containment / reactor building 11:50 a.m.
ABWR Test and Development Program 12:20 p.m.
Licensing Basis Agreement l
B -l
/
Federal Register Notice.
7590-01 NUCLEAR REGULATORY COP 9tISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS SUBCOMMITTEES.0NGENERALELECTRICREACTORS(ABWR)/ SAFETY PHILOSOPHY, TECHNOLOGY, AND CRITERIA Notice of Meeting The ACRS Subcommittees on General Electric Reactors (ABWR)/ Safety Philosophy, Technology, and Criteria will hold a joint meeting on January 7, 1987, Room 1046, 1717 H Street, NW, Washington, DC.
The entire meeting will be open to public attendance.
The agenda for the subject meeting shall he as follows:
Wednesday, January 7, 1987 - 9:00 A.M. Until the conclusion of business The GE Reactors Subcommittee will begin its review of the ABWR.
This will be a preliminary session to explore the status of this project and to be briefed on efforts regarding a licensing basis agreement between GE and the NRC.
A current description of the ABWR is sought as well as schedules from GE and the Staff.
The SPTC Subconnittee will review the status of the NRC Staff's work on the Safety Goal Policy and on USI A-17. " Systems Interactions on Nuclear Power Plants."
Oral statements may be presented by members of the public with the concurrence of the Subcomittee Chair. nan; written statements will be accepted and made available to the Committee.
Recordings will be pennitted only during those portions of the meeting when a transcript is being kept, and questions may be asked only by members of the Subcommittee, its consultants, and Staff.
Persons desiring to make oral statements should notify the ACRS staff member named below as far in advance as is practicable so that appro-priate arrangements can be made.
i be Y.
During the initial portion of the meeting, the Subcomittee, along with any of its consultants who may be present, may exchange preliminary views regarding matters to be considered during the balance of the meeting.
The Subcommittee will then hear presentations by and hold discussions with representatives of the NRC Staff, its consultants, and other interested persons regarding this review.
Further information regarding topics to be discussed, whether the meeting has been cancelled or rescheduled, the Chairman's ruling on recuests for the opportunity to present oral statements and the time allotted therefor can be obtained by a prepaid telephone call to the cognizant ACRS staff member, Mr. Richard Major (telephone 202/634-1414) between 8:15 A.M. and 5:00 P.M.
Persens planning to attend this meeting are urged to contact the above named individual one or two days before the scheduled meeting to be advised of any changes in schedule, etc., which may have occurred.
i Date t %-/5-R Ol m
11orton W. LYbarkin, Rssistant Executive Director for Project Review
J B4 m
Fdered Registee / Vol gr. No. 345 / siosiday, Defersdner Igl M 98edenis I
subsections (c)(4). (s) and (9NB ef Further informsties regneding sepism Committee. Discuss asyks br flature i
section H2h of Tade 5.Unsed Samans to be discussed, whether the meeting meeting with NRC r a--t-s-.-s; Cpde.
hos been caneelled or reacheduled, tim '
2 M psm-J'X p ara ctf Chairman's ruling on vagueses Apr the Subcommittee Activity (Open)--Hear
- 1. Date: Jensory 12.19er Time: 8.00 a a le Sepp.m opportunity Io present erof statements and docuse ACRS =.a.n,-.-ates,,eyerg Room:415 and the time allotted therefor can be regarding seismic reeweineWee ofer Progranr Thde unseelsig w#f powiege obtained by a peepend Iolophone ceN fu>
Dinkle Camyan Nusammr 74mmt.-
.oppaaetfees subenkled for Mmeowns the cognizano ACRS stefFmembee, Mr.
3:mp.m-&J0p.m.t Inipmeed t.(ght. T-and 6Esteriaal Oryonneseene.
Richard Major (telephone: amt/858-14141 Waterineseante(OpenFDiocese submitted to Genere! Progroms, br between 8:15 aa and 5m p.st pWrsons proposed ACRS report le the NRC' - *O pre $ec's bestuuss aRev July 1,1sg7.
planning to aused this meeting are regarding the characteristia et
- 2. Da te: January 15-?e. leef urged to contact the above===ad improved light water reactore.
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Timmat aos aa to aetpsas.
Individual one or twa days before the.
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- I*"*! 8 388F I
Ramsu:4ss scheduled meeting to be advised of any l
6 Program: His mesefag will rewsew chanamn in adadah.ses.,which may Aso.m.-eJeameAteduqr waab ARC l
applications submitted be har== i=. have occuared.
Executive Directorfor Operations and Hinterical Ortsnanatrona.
Dated. December is, tems, (Open/ClosedFDisease proposed NRC" submiumd ie Gennal programs. Ier
&mnas C. Recoeissa.
Staff Reorganisation and eseipuneet et F**9**'* b*S'** *K
- h*' 5"El 1 19W Assistant En ective Directar)br TecluucalP* * *"*I**b ** W ** A O *
- 3. Date: January 22-2 Alas act,,,is,,,
activities.
Time: 800 a.m. to 5.00 pa (m Doc. es-2 eon Pned u M s e W Portions of this sesalon wi!! he closed Room:415
. as necessary to discuss internal NRC Program: Then sneetag mit renew
' '. personnet rules and practices as well as applications submitted for Museums information the release of which would and Historical Organizations.
. r__, Cosnsmasse on Reestar represent a cleanly unwarranted a
submitted to General Programs, for Safeguards, Neciaar Reguissory invasion of personalprivacy.
Projects i,
-a efter brPy 7. 79er'.
Comaussiong RAmetag Agunsen RMo.m.-MM cm Sysfams 4.Date:lanuary 29-30,1987 Interact / orts (OpenFBriaFmg and Time: 8 ott e.m. to 5 00 p.m.
In etaprdance with the purposes el discuuion of NRC Staffresolution of Room:(15 sections 29 and 182b. of the Atemic ACRS comments in its report of nfay13 Program: This meeting wiff review Energy Act (42 U.S.C. 2039, 2232h), the toes on Proposed Resokstion of USI A-appbearmns submitted for Museuras Adviacry Committee on Emaction 17 Systems Interactions in NacArar and Historical Organizations Safeguards will hold a meeting on Power Ments.
submitted to Genera! Programs for Ja rmary 8-10.1987. in Room 1046,1717 M ras e.st-JJffs e.ar Sbppreesise profects begirming after July 1,1967 Street NW., Washington. DC. Notice of poo/Byposs (Open)-Discuss proposed as.phs, y peecs,y, this meeting was pubbshedin the priority fee mechstion of Generte Issue Advisory Corr.matee Mancgemast @er Federal Register on November 2D,1g88.
61 SRV Discharge IJae Break in the (m Doc. as-2stnt Filed 12-24-as.tu am4 Thusadey,Jesuary ALisa, Airspace of ha 1/Mk D Consakammenen.
12:t$as 22Ms%on: Appointnnentof 8:Ma.n-99c.ar.tReport ofACRS NewAC)RShienaber(ClosedFDesmane Choirmerr(OpenFThe ACRS Chettmas the qualificaturns sicandidates wiff report briefly w..a items of proposed for appoiannent to the AGS$
LEAR REGlJLATORY current interest to the Committee.
nie sessian wel be closed as AWo m-tNSa.rrr.t Cenem/K/ectric necessary Ie d=e== laternal myany Advfoory Committee on Reactor A d * *'# 8 # 8 IUP " d CA'8'87,
Personel ponenes and proceses as wuN Discuss scope of review. -rr-ae information the reiesse ad which
[g*s' p'"g g ***
crHerie, e4c., regording the preReensing would represent a clearly userarrested agreement for considnetion of thie invesion of personal prisesy.
Philosophy, Tecimology, and Crtterts-project.
2.m p m -e.M p.m :lagsm eed E.ight pm Portiene of this scenten wi5 be closed WaterReacars (OpenFIhacias 5
The Fedsan! Esgimeur pubbshed on es necesery to dieeves Prwrietery proposed ACRS report to the NRC i
Fridsy.Desember 19 tses(M FR 45671y Information applicable to this preject.
regarding the characteristies af i
ccntauwd noense of a jeens meetene el 11.#o ne-J2WNecar Meehar wrM irnproved light wefee reacture.
l the ACRS u.* trees oo Geners!
NRCDnecape. Ogice af Abeleer Keerese i
Elecent Reactars (ABWR)/ Safety Regu/atsen (Opeo)-Discues itsune of Saturday, january se,1s57 I
philosophy. T M-g. aast Criteris to mutmet isseme regarding the Nnc AN e.as-12:30 pal ACAS Repsess se i
be held am Wedmeedwy. January 7 Tes7 raguieNwy process and safeepelered NRC(Open/ Closed) rhamaa peepoemd 9100 mm. Rooms toes.1717 H Soset, mattees.
ACRS reports to the NRC regarding i
NW., Washagerm. DC.To the extees imp m-2Mp mr Asp 4wentativir of items considered during this sneeting pr:ctisal the emettag usel be open am NNCSofety CoodPMry(OpenF.
Portions of this session will be closed, public attenchase. Neuewar, partione se Subcommettee report and brieRag as necessary to discuss Proprietary t
j thz meeeng neer he chmed to disemos regarding the efetee of NRC activittee Information applicable to the matesso inasnaatma proeished he agency from a regarding iwrplernensattest of the NRC being aEscussed f; reign searce 6POLA lhemption (b)2 Safety Goel Policy.
Sulrommiate Act/riese (Open/
1.10p nmf JIPAnt.t ACMS' and safeguards informesism(FORA '
2.4pn-2SPpMrfuAme Ace winne Emenspian(b)si ABetheeiemms (Open)-Discwee enticipered ACR5 CheedFHeer and discuse reports of repeding this smeeting resseh the samme - subcoramittee acervtues and toyune designated Acts sebcommuteses as previous)y sansM proposed for consideredien by the fut regarding smisepelmesd aeMwines
- ~
ATTACHMENT C o
e' LIST OF SLIDES 1.
A Presentation to the Joint ACRS Subcommittee on ABWR Certification Program - Presented by GE Company, Washington, D.C., January 1987 44 slides.
2.
Information Regarding Specific ACRS Questions - 16 slides Containment Capability Given a Core Melt Fire Protection Protection Against External Attack Dedicated Systems Filtered Vents for Containment Design Features to Protect Ground Water Given a Severe Accident What is the Safety Goal Sought By GE Seismic Design Basis / Rick Methods for Improved Maintenance and Self-Testing Automation of Controls 3.
NRR Staff Presentation to the ACRS -
Subject:
NRC Licensing Program, Advanced Boiling Water Reactor (ABWR), Ralph Caruso, January 7-8, 1987. - 9 slides
=
e