ML20137F316

Informs That Staff Determined That Overall Quality of Sys Drawings & Piping & Instrumentation Drawings Inadequate to Support Review.Staff Assessment of Issue Encl

ML20137F316
Person / Time
Site:	05200003
Issue date:	03/27/1997
From:	Martin T NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9704010058
Download: ML20137F316 (4)

Text

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, hw r,b p- 4 UNITED STATES

, g j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20656-0001 l /

%***j March 27, 1997 i

Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities

[JJM  !

Nuclear and Advanced Technology Division '

Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230

SUBJECT:

WESTINGHOUSE AP600 STANDARD SAFETY ANALYSIS REPORT (SSAR) - KEY ISSUE 1 i

Dear Mr. Liparulo:

l In a letter dated January 7,1997, the Nuclear Regulatory Commission (NRC)  !

identified key AP600 issues. These issues were identified because of their l potential to become critical path issues for completion of the AP600 design  !

review. Key Issue 1 involved the level of detail of information in the SSAR. l Reinsertion of specific information in SSAR tables and text is proceeding on  !

an item-by-item basis, as requested by Westinghouse. Additionally, in {

Revision 11 of the SSAR, Westinghouse increased the number of systems and system information in Table 3.2-3, AP600 Classification of Mechanical and l

Fluid Systems, Components, and Equipment. These changes have significantly l improved the table and the staff's ability to verify necessary system informa- '

tion. The staff has not completed its review of Table 3.2-3, but believes any l outstanding issues on this information can now be addressed on an item-by-item l basis.

In reviewing the SSAR, the staff has determined that the overall quality of  :

the system drawings, and piping and instrumentation drawings (P& ids) is inadequate to support the review. In Revision 6 of the SSAR, the staff ,

identified that several P& ids were removed from the SSAR. The deficiency was '

identified in requests for additional information for Chapters 9,10, and 11.

Subsequently, Westinghouse replaced some diagrams, which the staff found unacceptable because they were illegible and/or lacked sufficient detail. In response, Westinghouse provided a set of proprietary P& ids for the staff.

This was an acceptable interim solution to support continuance of the review but did not resolve the issue. Enclosed is the staff's assessment of the issue.

I J

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1 Mr. Nicholas J. Liparulo March 27,1997 If you have any questions regarding this matter, you can contact Diane Jackson at (301) 415-8548.

Sincerely, original signed by: l Thomas T. Martin, Director 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 TMartin PUBLIC MSlosson TRQuay TKenyon BHuffman JSebrosky l DJackson ACRS (11) JMoore, 0-15 B18 l WDean, 0-17 G21 HWalker, 0-8 D1 JRaval, 0-8 D1 LMarsh, 0-8 D1 CLi, 0-8 D1 BThomas, 0-8 01 GHolahan, 0-8 E2 4

9 DOCUMENT NAME: A:P& IDS.LET n h,. . ..,y . w. t. i i. m. 6.m C . Copy wkhout attachmenU.nege 'U = Copy wth attachment / enclosure "N" = No copy 0FFICE PM:PDST:DRPM _ , D:PDST:DRPM l D:DSPR ibh- l l l

, NAME DTJackson:sg (/P TRQuay C N TTit'artin

DATE 03h/ /97 ~ () 03/1t/97 03/t?/97 0FFICIAL RECORD COPY

. 2 i .

i

!~

Mr. Nicholas J. Liparulo Westinghouse Electric Corporation Docket No.52-003 AP600 i cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director I i

^

Advanced Plant Safety & Licensing Advanced Reactor Programs i Westinghouse Electric Corporation Nuclear Energy Institute i 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 Advanced Plant Safety & Licensing Doc-Search Associates  ;

Westinghouse Electric Corporation Post Office Box 34  !

! Energy Systems Business Unit Cabin John, MD 20818 '

) Box 355 Pittsburgh, PA 15230 Mr. James E. Quinn, Projects Manager 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 .  ;

i 11921 Rockville Pike Mr. Robert H. Buchholz  ;

l Suite 350 GE Nuclear Energy  ;

Rockville, MD 20852 175 Curtner Avenue, MC-781 San Jose, CA 95125 Mr. Sterling Franks j U.S. Department of Energy Barton Z. Cowan, Esq. i NE-50 Eckert Seamans Cherin & Mellott >

19901 Germantown Road 600 Grant Street 42nd Floor Germantown, MD 20874 Pittsburgh, PA 15219 l Mr. S. M. Modro Mr. Ed Rodwell, Manager Nuclear Systems Analysis Technologies PWR Design Certification i Lockheed Idaho Technologies Company Electric Power Research Institute  ;

Post Office Box 1625 3412 Hillview Avenue Idaho Falls, ID 83415 Palo Alto, CA 94303  !

i Mr. Frank A. Ross Mr. Charles Thompson, Nuclear Engineer i U.S. Department of Energy, NE-42 AP600 Certification Office of LWR Safety and Technology NE-50 19901 Germantown Road 19901 Germantown Road Germantown, MD 20874 Germantown, MD 20874 I

l J

- u Content of the Standard Safety Analysis Report (SSAR) - Key Issue 1 In reviewing the SSAR, the staff has determined that the overall quality of the system drawings, and piping and instrumentation drawings (P& ids) is inadequate to support the review. The standard review plan prescribes that the staff's review includes the system P& ids to determine, in part, system flows and interfaces, equipment availability, and potential bypass routes.

The P& ids are also used to verify information, such as, physical divisions between safety-related and non safety-related portions of a system, the system classification changes, and the ability for system isolation. Using the SSAR information (descriptions, tables, diagrams, and drawings), the staff must be able to conclude that the system designs are adequate to meet the regulations as set forth in the General Design Criteria.

Westinghouse needs to provide legible P& ids and system figures in the SSAR with sufficient detail including, system interconnections, piping classifica-tions, seismic and quality group interfaces, and instrumentation and controls for all AP600 systems.

Enclosure