ML20134P311

Requests That W Revise Ssar to Reflect Listed Info

ML20134P311
Person / Time
Site:	05200003
Issue date:	02/20/1997
From:	Martin T NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9702250331
Download: ML20134P311 (3)

Text

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WASHINGTON, D.C. 20655-0001

\..."..p'e February 20, 1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis

' Nuclear and Advanced Technology Division i' Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

PIPING FUNCTIONAL CAPABILITY ISSUE FOR THE WESTINGHOUSE AP600 ADVANCED REACTOR DESIGN

Dear Mr. Liparulo:

In the AP600 Draft Safety Evaluation Report (DSER), NUREG-1512, dated Novem- l ber 1994, the staff provided you its review conclusion relative to the design l criteria to be used to ensure the functional capability of piping. These 1 criteria are necessary because the ASME Code,Section III does not address the functional capability of piping systems; rather, it addresses pressure boundary integrity. Functional capability of a piping system might be lost if, for example, displacements were large enough to " crimp" a pipe cross I section and thus reduce the flow area while still maintaining the structural '

integrity of the pipe. As stated on the DSER, the use of the criteria in NUREG-1367, " Functional Capability of Piping Systems," dated November 1992 ,

i provides the staff assurance that the required flow area of the pipe will be maintained under design basis loads. Subsequent to the issuance of the DSER, j

there have been ongoing discussions between Westinghouse and the staff on this  !

issue. However, as of Revision 10 to the standard safety analysis report (SSAR) Section 3.9, the Westinghouse position still does not meet the func-tionality criteria that the staff has established for all previous advanced design certification. Therefore, you are advised to revise the SSAR to reflect the following information:

The AP600 design for piping functional capability should implement the criteria in Section 9, " Conclusions" of NUREG-1367, with the following clarification:

When slug-flow loads are combined with other design basis loads, e.g., '

safe shutdown earthquake, pipe break loads, etc., then ASME Level D allowable stresses are acceptable for functional capability. When slug-flow loads are only combined with pressure, weight, and other sustained mechanical loads, then ASME Level C allowable stresses should be used, and the 0.25 Sy limit for steady-state loads does not apply. The 0.25 Sy limit applies for steady-state loads, which consist of pressure and dead weight loads only.

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If you have any question in this matter,' you can, contact Ms. Diane Jackson, at-(301) 415-8548. -

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Sincerely, 5.g ^ l'

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original signed by: e Thomas T. Martin, Director  ;

Division of Reactor Program Management Office of Nuclear Reactor Regulation l Docket No.52-003 f

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I Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation 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 1776 Eye Street, N.W.

P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. Cindy L. Haag Ms. Lynn Connor l Advanced Plant Safety & Licensing Doc-Search Associates  !

Westinghouse Electric Corporation Post Office Box 34 Energy Systems Business Unit Cabin John, MD 20818  :

Box 355 l Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager i LMR and SBWR Programs Mr. M. D. Beaumont GE Nuclear Energy Nuclear and Advanced Technology Division 175 Curtner Avenue, M/C 165 Westinghouse Electric Corporation San Jose, CA 95125 One Montrose Metro 11921 Rockville Pike Mr. Robert H. Buchholz Suite 350 GE Nuclear Energy Rockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks U.S. Department of Energy Barton Z. Cowan, Esq.

NE-50 Eckert Seamans Cherin & Mellott 19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification Lockheed Idaho Technologies Company Electric Power Research Institute Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303 Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 ,

19901 Germantown Road 19901 Germantown Road l Germantown, MD 20874 Germantown, MD 20874 i

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