ML20134H276

Notification of 970211-12 Meeting W/Westinghouse in Rockville,Md to Discuss Source Term Issues Related to AP600

ML20134H276
Person / Time
Site:	05200003
Issue date:	02/05/1997
From:	Kenyon T NRC (Affiliation Not Assigned)
To:	Quay T NRC (Affiliation Not Assigned)
References
NUDOCS 9702110228
Download: ML20134H276 (4)

Text

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February 5,1997  !

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. MEMORANDUM T0: Thrdore RL Quay, Director

} Standardization Project Directorate ,

Division of Reactor Program Management, NRR i FROM

Thomas,J. Kenyon, Project Manager original signed by:

} Standa~rdization Project Directorate '

, Division of Reactor Program Management, NRR '

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SUBJECT:

NOTICE OF MEETING WITH WESTINGHOUSE TO DISCUSS SOURCE TERM j ISSUES ON THE AP600 i-DATE AND TIME: February 11 and 12, 1997 8:30 a.m. - 5 p.m.

LOCATION: Polestar 1 First Street Los Altos, California .

PURPOSE: To discuss source term issues related to the AP600. See attached agenda.

PARTICIPANTS *: EC hstinahouse R. Each B. McIntyre J. Lee D. Leaver J. Kudrick J. Li M. Snodderly J. Grover ,

J. Sebrosky, et al.

Docket No.52-003 i

Attachment:

As stated '

cc w/ attachment: ,

See next page i

• Meetings between the.NRC technical staff and applicants or licensees are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to " Commission Policy Statement on Staff Meeting Open to the.Public,"-59 Federal Reaister 48344, 9/20/94.

However, portions of this meeting may be closed to protect Westinghouse proprietary information. Members of the public who wish to attend should contact-me a,t (301) 415-1120. ,-

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Westinghouse Electric Corporatior, Docket No.52-003 l cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 Germantown, MD 20874 Pittsburgh, PA 15230 Mr. Ronald Simard, Director Mr. B. A. McIntyre Advanced Reactor Program Advanced Plant Safety & Licensing Nuclear Energy Institute Westinghnuse Electric Corporation 1776 Eye Street, N.W.

Energy Systems Business Unit Suite 300 Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Mr. John C. Butler Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Mr. James E. Quinn, Projects Manager Pittsburgh, PA 15230 LMR and SBWR Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, M/C 165 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. P.obert H. Buchholz 11921 Rockville Pike GE Nuclear Energy Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.

U.S. Departmen* of Energy Eckert Seamans Cherin & Mellott NE-50 600 Grant Street 42nd Floor 19901 Germantown Road Pittsburgh, PA 15219 Germantown, MD 20874 Mr. Ed Rodwell, Manager Mr. S. M. Hodro PWR Design Certification Nuclear Systems Analysis Technologies Electric Power Research Institute Lockheed Idaho Technologies Company 3412 Hillview Avenue Post Office Box 1625 Palo Alto, CA 94303 Idaho Falls, ID 83415 Mr. Charles Thompson, Nuclear Enginer-AP600 Certification NE-50 19901 Germantown Road Germar'tyn, MD 20874

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~ l AGENDA FOR AEROSOL MEETING WITH WESTINGHOUSE FEBRUARY 11 and 12, 1997 February 11. 1997 8:30 - 9:00 J. Lee Key Technical Licensing Issues for Aerosc1 i Behavior in the AP600 Containment following a Design Basis Accident 9:00 - 10:00 D. Powers Additional Analyses of Aerosol Behavior in the AP600 Constrainment under Postulated Accident Conditions  :

1 10:00 - 12:00 West. Discussion of the NAUA code used by Westinghouse f to calculate aerosol removal coefficients,  !

including pedigree, customizations performed, l code VW, QA, and code inputs used and outputs i obtained in calculating the aerosol removal rates. i 12:00 - 1:00 Lunch 1:00 -

5:00 West. Discussion of the sensitivity analyses that were performed for the NAUA code used by Westinghouse to consider uncertainties in processes and param-eter values West. Discussion of the nodalization of the AP600 containment aerosol sedimentation area and geome-try, the rationale for level of specification, anti the bases for the boundary conditions for each node to determine aerosol removal coeffi-cients.

West. Discussion of the rationale for assuming that the AP600 containment atmosphere would be homoge-neously mixed following a postulated DBA.

February 12. 1997 8:30 - 12:00 West. Discussion of related experimental data or pub-lished literature.

West. Discussion of the technical bases for the specif-ic values for the aerosol removal coefficients for the proposed AP600 containment design follow-ing a postulated DBA.

Attchment

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l West. Discussion of aerosol removal rates and l i associated uncertainty distribution. Discussion of the assumption that the phoretic processes are insensitive to the higher steam condensation rates at later times. '

l 12:00 - 1:00 Lunch 1:00 - 3:00 West. Discussion of the applicability of the CONTAIN and NAUAHYGROS codes for predicting phenomenological effects on boundary layer deple-  ;

tion and on phoretic processes under harsh envi- 1 ronmental conditions.

West. Discussion of the basis for the aerosol removal mechanisms used in the MAAP models for severe accidents, and how they compare to SANDIA's best estimate.

3:00 - 3:30 All Closing remarks; Next actions In addition, sample run(s) will be performed during the meeting using the NAVA code usea by Westinghouse to calculate aerosol removal coefficients.  :