ML20127M694

Discusses Preliminary Staff Evaluation of ABWR Severe Accident Performance

ML20127M694
Person / Time
Site:	05200001
Issue date:	01/25/1993
From:	Son Ninh Office of Nuclear Reactor Regulation
To:	Marriott P GENERAL ELECTRIC CO.
References
NUDOCS 9301280269
Download: ML20127M694 (3)

Text

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i January 25, 1993 Docket No.52-001 Mr. Patrick W. Harriott, Manager Licensing & Consulting Services GE Nuclear Energy 175 Curtner Avenue San Jose, California 95125

Dear Mr. Marriott:

SUBJECl: PREllHillARY staff EVALVAT10t1 Of THE ADVAt1CED BOILING WATER REACTOR (ABWR) SEVERE ACCIDENT PERf0RMAf1CE This refers to a draf t copy of the staff's prelininary evaluation of the ABWR design performance under severe accident conditions which was sent to GE _

Nuclear Energy (GE) on September 22, 1992. The staff has recently completed an evaluation of the containment design to withstand axial concrete ablation of 1.5 meters and determined that GE has not adequately addressed this condition. The staff requests that GE perform an engineering analysis (best-estimate analysis) based on specific configuration of the junction between the lower part of the pedestal and the basemat structures including consideration of the anchorage details at the junction. In the meantime, this remains an open item.

Enclosed with this letter is our preliminary safety evaluation based on the information provided in the standard safety analysis report. I request that this enclosure be the basis for a conference call in the week of January 25, 1993. Please contact me at (301) 504-1135 to arrange this call.

Sincerely, (Original signed by)

Son Q. flinh, Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors -

and License Renewal Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure: ]

See r, ext page R Lsi gl M u m :

Docket file PDST R/f TMurley/FMiraglia DCrutchfield PDR WTravers CPosiusny SNinh RBorchardt JNWilson PShea GGrant, EDO JMoore, 15B18 ACRS (11) JMonninger, 8D1 JKudrick, 8D1 RBarrett, 801 HAshar, 7H15 LShao, RES J0'Brien, RES ,

[ BHardi[n)RES ty 0FC: LA:PDST:ADAR P!4:PDST: ADAR PM:PDST:ADAR S : POST:ADAR f NAME: PShe CSNnh:tz CPosiusny JNWilson DATE: 0 /c Of/? 01/i//93' f01//f/93 r]

OfflCIAL RECORD COPY: ABWib993 4.SQN Mk/

9301280e67 930125 ADOCK 05200001

' bob f PDR A PDR

e GE Nuclear Energy Docket No.52-001 Mr. Robert Mitchell Mr. Joseph Quirk General Electric Company GE Nuclear Energy 175 Curtner Avenue Mail Code 782 San Jose, California 95114 General Electric Company 175 Curtner Avenue Mr. L. Gifford, Program Manager San Jose, Califernia 195114 Regulatory Programs GE Nuclear Energy '

12300 Twinbrook Parkway .

l Suite 315 Rockville, Maryland 20852 Director, Criteria & Standards Division  !

Office of Radiation Programs "

4 U. S. Environmental Protection Agency 401 M Street, S.W.

Washington, D.C. 20460 Mr. Daniel F. Giessing V. S. Department of Energy NE-42 1 Washington, D.C. 20585 ,

l l

Mr. Steve Goldberg Budget Examiner 725 17th Street, N.W. ,

Room 8002 Washington, D.C. 20503 Mr. Frank A. Ross

- U.S. Department of Energy, NE-42 Office of LWR Safety and Technology '

19901 Germantown-Road Germantown, Maryland 20874 Mr. Raymond Ng l 1776 Eye Street, N.W.

Suite 300 '

Washington, D.C. 20006 Marcus A. Rowden, Esq. ,

Fried, Frank, Harris, Shriver & Jacobson 1001 Pennsylvania Avenue, N W. .

Suite 800  :

- Washington, D.C. 20004 Jay M. Gutierrez, Esq.

Newman & Holtzinger, P.C.

1615 L Street, N,W.

Suite 1000-

-Washington, D.C. 20036 ,

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--r Specific Area: Evaluation of the containment to withstand axial concrete

, ablation of 1.5 meters Evaluation: GE has not addressed this condition.

Figure 3.18-18 of the advanced boiling water _ reactor -

standard safety analysis report-indicates that the thickness- '

of the fill concrete above the basemat -liner plate is 1.57m.

If the CCI ablation is limited to 1.5m.. .it can be assessed

-that the basemat liner plate will- maintain its integrity: -

j under the postulated ablation. However, depending upon the extent of radial spread of the ablation, the-integrity of -

the sumps, and the pedestal wall, anchorages -could get affected. Thus, without a better-description of the  ;

ablation progression, and-details 1 of the pedestal: wall .

anchoragos in the fill concrete and the basemat, this item cannot be adequately addressed. . Therefore, the staff requests that GE perform an engineering analysis (best-estimate analysis) based on. specific configurationaof the-junction between the lower.part of the pedestal and the

.. basemat structures including consideration of the anchorage-details at the junction. In the meantime, this remains an 4 open item.

i Enclosure

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