ML20149J299

Notification of 970804-0815 Meeting W/W in Rockville,Md to Discuss AP600 Structural Design of Nuclear Structures.Draft Agenda Encl

ML20149J299
Person / Time
Site:	05200003
Issue date:	07/25/1997
From:	Joseph Sebrosky NRC (Affiliation Not Assigned)
To:	Quay T NRC (Affiliation Not Assigned)
References
NUDOCS 9707280154
Download: ML20149J299 (4)

Text

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g * ., July 25, 1997 i

I MEMORANDUM T0: Theodore R. Quay, Director Standardization Project Directorate l Division of Reactor Program Management, NRR l FROM: Joseph M. Sebrosky, Project Manager original signed by: >

i Standardization Project Directorate j Division of Reactor Program Management, NRR

SUBJECT:

NOTICE OF MEETING WITH WESTINGHOUSE TO DISCUSS THE AP600 STRUCTURAL DESIGN OF NUCLEAR ISLAND STRUCTURES DATE AND TIME: August 4, through' August 8, 1997 - 8 a.m. - 5 p.m.

[ August 11 through August 15, 1997.- 8 a.m. - 5 p.m.

LOCATION: Westinghouse Electric Corporation One Montrose Metro

11921 Rockville Pike i Rockville, Maryland 20852 Suite 107

-PURPOSE: The purpose of the meeting is to complete the review of the i seismic and structural design of the AP600 nuclear island

! structures including the' nuclear island foundation mat. A Jraft agenda is attached.

j-PARTICIPANTS *: NRC WESTINGHOUSE G. Bagchi R..Orr' T. Cheng ~D. Lindgren, et al.

J. Sebrosky, et al.

Docket No.52-003 ,

Attachment:

As stated cc w/att: See next page

• 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 Reoister 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 at (301) 415-1132.

DISTRIBUTION:

NRC FILE CENTER COPY sc c.33 D W' 3 DOCUMENT NAME: A:STRUC AU.N0T To ecceive e copy of this document,IndceTe in the box: "C" = Copy without ettechment/ enclosure *E* = Copy with attachment / enclosure *N" = No copy 0FFICE PM:PDST:DRPM _

D:PDST:DRPM l

.NAME JMSebrosky:sg D h TRQuay W/o DATE 07/W/97 L 07/n'/97 / W 0FFICIAl. RECORD COPY 9707280154 970725 PDR ADOCK 05200003 A PDR

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DISTRIBUTION: Memorandum to Theodore R. Quay. Dated: July 25,1997 Docket File i 4

PUBLIC I l

PDST R/F SCollins/FMiraglia, 0-12 G18 TTMartin, 0-12 G18 RZimmerman, 0-12 G18

. MSlosson SWeiss J TJKenyon

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DTJackson 1 WCHuffman JMSebrosky l WDean, 0-5 E23  !

JMoore, 0-15 B18 ACRS (11) ,

GBagchi, 0-7 H15 TCheng, 0-7 H15 )

RPichumani, 0-7 HIS  ;

RRothman, 0-7 HIS PMNS (e-mail)  !

OPA (e-mail) i 1

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Westinghouse Electric Corporation Docket No.52-003 cc: Mr. Nicholas J. Liparulo, Manager Mr. Frank A. Ross Nuclear Safety and Regulatory Analysis U.S. Department of Energy, NE-42 i

Nuclear and Advanced Technology Division Office of LWR Safety and Technology Westinghouse Electric Corporation 19901 Germantown Road P.O. Box 355 Germantown, MD 20874

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Pittsburgh, PA 15230 i

Mr. Ronald Simard, Director Mr. B. A. McIntyre -Advanced Reactor Program 1 Advanced Plant Safety & Licensing Nuclear Energy Institute l t

Westinghouse Electric Corporation 1776 Eye Street, N.W. l Energy Systems Business Unit Suite 300

Box 355 Washington, DC 20006-3706 Pittsburgh, PA 15230 Ms. Lynn Connor Ms. Cindy L. Haag Doc-Search Associates Advanced Plant Safety & Licensing Post Office Box 34 Westinghouse Electric Corporation Cabin John, MD 20818 Energy Systems Business Unit Box 355 Dr. Craig D. Sawyer, Manager Pittsburgh, PA 15230 Advanced Reactor Programs GE Nuclear Energy Mr. M. D. Beaumont 175 Curtner Avenue, MC 754 Nuclear and Advanced Technology Division San Jose, CA 95125 Westinghouse Electric Corporation One Montrose Metro Mr. Robert H. Buchholz l

11921 Rockville Pike GE Nuclear Energy l Suite 350 175 Curtner Avenue, MC-781 Rockville, MD 20852 San Jose, CA 95125 Mr. Sterling Franks Barton Z. Cowan, Esq.

U.S. Department 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. Modro 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 Engineer AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874

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Aaenda for the Final Review Meetina of Structural Desian of AP600 Nuclear Island Structures 1

i DAlt: August 4 through August 8, 1997 Tonics:

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1. Review the construction' sequence, possible interface problems and the i

generation of loads due to the construction sequence for the design of j the foundation mat and. lower elevation structures. 6

2. Review the site conditions (for example, uniform and non-uniform sites) and geotechnical related issues including the characterization of the 4

soil stiffness variability with the foundation mat foot print.

3. Review the final design calculations of critical sections related to the.

foundation mat and exterior embedded walls.

h 4.- Resolve issues identified from the review of SSAR revision changes, if

any, p

l 5. Resolve open issues related to SSAR Sections 2.5.4, 3.7.2 (SSI) and j 3.8.5. j 1

i QAlg: August 11 through August 15, 1997 l

4 j Tonics: i 4

1 1. Review the model revision and new SASSI analysis (incorporation of design changes due to post-72 hour actions, and live and snow loads in the  :

l j seismic model and analysis results) of the nuclear island structures.  !

3 The staff review will also cover the adequacy of the site condition

[

selected by Westinghouse for the new SASSI analysis.

2. Review the new 30 ANSYS analysis (modeling and results) of the shield building roof structures (including the PCCWST and fire tank). The staff review will also cover the adequacy of the revised model due to design changes of the increased water flow required for post-72 hour actions, ,

and the incorporation of snow load in the 3D model. I

3. Review Westinghouse's justification of the design adequacy of the steel containment shell against the thermal shock due to post-72 hour actions.

4. Review design calculations for critical sections of the auxiliary building and shield building roof structures (including the PCCWS tank).

5. Review the design of.the fire protection system tank (FPST).

6. Resolve issues identified from the review of SSAR revision changes, if any.

7. Resolve open issues related to SSAR Sections 3.7.1, 3.7.2, 3.8.2 and 3.8.4.

Attachment

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