ML20148H144

Forwards Request for Addl Info Re Review of AP600 Containment Design Basis Analysis in Section 6.2

ML20148H144
Person / Time
Site:	05200003
Issue date:	06/06/1997
From:	Huffman W NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9706090248
Download: ML20148H144 (3)

Text

I 4 e June 6,1997 l

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l Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis ,

Nuclear and Advanced Technology Division I Westinghouse Electric Corporation j P.O. Box 355 i

Pittsburgh, PA 15230 l

SUBJECT:

AP600 CONTAINMENT DESIGN BASIS ANALYSIS REQUEST FOR ADDITIONAL INFORMATION (RAI) i

Dear Mr. Liparulo:

In support of the AP600 design certification review, the Nuclear Regulatory Commission staff is evaluating the Westinghouse containment design basis analysis in Section 6.2 of the AP600 Standard Safety Analysis Report. Based on its review of the containment subcompartment pressurization analysis, the staff has a request additional information. The RAI is provided in an enclo-sure to this letter.

If you have any questions regarding this matter, you can contact me at (301) 415-1141.

Sincerely, original signed by:

William C. Huffman, Project Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003

Enclosure:

As stated cc w/ enclosure: See next page DISTRIBUTION:

Docket File PDST R/F MSlosson PUBLIC SWeiss TRQuay TKenyon BHuffman JSebrosky * [,

DJackson JMoore, 0-15 B18 WDean, 0-5 E23 )

ACRS (11) CBerlinger, 0-8 H7 MSnodderly, 0-8 H7 JDawson, 0-8 H7 e m 23 NRC Hi.E BEEER CDPV DOCUMENT NAME: A:DWN3-CNT.RAI To roccive a copy of this document,Ir.dicate in the bos: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure *N" = No copy j OFFICE PM:PDST:DRPM l D:PDST:DRPM l l l WCHuffman:skirkkTRQuay 9 4?

NAME DATE 06/(o/97 '06/ 6./97

'IAL RECORD COPY 970609024a 970606 PDR ADOCK 05200003 A PDR

7 . s, i Mr. Nicholas J. Liparulo \

Westinghouse Electric Corporation Docket No.52-003 AP600 cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit P.O. Box 355 1776 Eye Street, N.W.

Pittsburgh, PA 15230 Suite 300 Washington, DC 20006-3706 Mr. Cindy L. Haag Ms. Lynn Connor I l Advanced Plant safety & Licensing Westinghouse Electric Corporation Doc-Search Associates Energy Systems Business Unit Post Office Box 34 i l Box 355 Cabin John, MD 20818 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. S. M. Modro GE Nuclear Energy l Nuclear Systems Analysis Technologies j 175 Curtner Avenue, M/C 165 Lockheed Idaho Technologies Company San Jose, CA 95125 Post Office Box 1625 Idaho Falls, ID 83415 i Mr. Robert H. Buchholz Mr. Sterling Franks GE Nuclear Energy 175 Curtner Avenue, MC-781 U.S. Department of Energy San Jose, CA 95125 NE-50 19901 Germantown Road Barton Z. Cowan, Esq.

Germantown,1E) 20874 Eckert Seamans Cherin & Mellott Mr. Frank A. Ross 600 Grant Street 42nd Floor Pittsburgh, PA 15219 U.S. Department of Energy, NE-42 Of.fice of LWR Safety and Technology Mr. Ed Rodwell, Manager l 19901 Germantown Road PWR Design Certification  :

Germantown, MD 20874 .

Electric Power Research Institute l 3412 Hillview Avenue Mr. Charles Thompson, Nuclear Engineer Palo Alto, CA 94303  !

AP600 Certification NE-50 19901 Germantown Road Germantown, MD 20874 4

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AP600 SSAR SECTION 6.2 REQUESTS FOR ADDITIONAL INFORMATION i

480.1050 State the breaks for which the NOTRUMP code rather than SATAN-VI, was used to calculate the mass and energy re, lease for the contain- ,

ment subcompartment analysis, and provide the rationale for using one code instead of the other for a given break. Also, for each code, provide a descriptive summary of the primary system nodalization as it pertains to the subcompartment analysis. That is, discuss any conservatisms made in the noding and releases that are specific to the subcompartment analysis (e.g., modeling of break node, assumed boiling regimes for heatup of primary fluid, etc.).

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! Enclosure L