ML20211Q106

Discusses Open Item Associated w/AP600 SER on Integrity of Reactor Coolant Pressure Boundary

ML20211Q106
Person / Time
Site:	05200003
Issue date:	10/16/1997
From:	Huffman W NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9710220103
Download: ML20211Q106 (3)

Text

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October 16, 1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division .

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

SUBJECT:

OPEN ITEM ASSOCIATED WITH AP600 SAFETY EVALUATION REPORT (SER) ON INTEGRITY OF THE REACTOR COOLANT PRESSURE BOUNDARY (RCPB)

Dear Mr. Liparulo:

The Civil Engineering and Geosciences Branch of the U.S. Nuclear Regulatory Commission has provided an SER input to the Standardization Project Director-ate related to Chapter 5.2 on Integrity of the RCPB. The input has an open item which has been extracted and designated as an FSER open item in the enclosure to this letter.

If you have any questions regarding this matter, you may 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/ encl: See next page DISTRIBUTION:

' Docket File PUBLIC

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DMatthews TRQuay g TKenyon BHuffman JSebroksy I DScaletti JNWilson JMoore, 0-15 B18 WDean, 0-5 E23 ACRS (11) TCollins. 0-8 E23 TMarsh, 0-8 D1 RYoung, 0-8 D1 GBagchi, 0-7 HIS RCaruso, 0-8 E2 GHsii, 0-8 E23 JHuang, 0-7 HIS

-GHolahan, 0-8 E2 JBrammer. 0-7 H15 Glainas, 0-7, 026 DOCUMENT NAME: A: CLASS-CV.3ER

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DATE 10/[$/97 10/ /97 10/@/97 Y OFFICIAL RECORD COPY *See previous concurrence 9710220103 971016 @ .m ADOCK 052000 3

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i SER OPEN ITEM ASSOCIATED WITH AP600 FSER SECTION 5.2.1.1 1

230.140F Per the definition of Reactor Coolant Pressure Boundary (RCPB) as defined in 10 CFR 50.2, the staff believes that most of the AP600 Chemical and Volume Control System (CVS) should be defined as RCPB piping. Although the CVS RCPB piping meets the exclusion require-l ments of 10 CFR 50.55a(c)(2), NRC Regulatory Guide 1.26, Revi-sion 3, would recommend that the CVS piping be constructed as ASME Code,Section III, Class 2. In addition, 10 CFR 50, Appendix A General Design Criteria 14, 30, and 32 emphasize that the reactor coolant pressure boundary components be designed, fabricated, erected, and tested to the highest quality standards practical.

1 In a letter to Westinghouse dated August 25, 1997, the staff

, identified its concern relative to the quality group classifica-

. tion of the portion of the CVS inside containment. In a letter

^ dated September 11, 1997, Westinghouse provided justification for its classification of the CVS. In a telecon with Westinghouse on October 1, 1997, the staff stated that the justification provided by the September 11, 1997, letter was insufficient. Westinghouse i committed to reexamine the design classification of the CVS piping

' and determine if additional design or testing features could be included to resolve the classification issue. Pending acceptable resolution of the CVS piping classification, the staff considers this an FSER Open Item.

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Enclosure l

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u Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 cc: Mr. B. A. McIntyre Mr. Russ Bell Advanced Plant Safety & Licensing Senior Project Manager, Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 I Street, NW P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Mr. 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 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energy 175 Curtner Avenue, MC-754 NE-50 San Jose, CA 95125 19901 Germantown Road Germantown, MD 20874 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Frank A. Ross 175 Curtner Avenue, MC-781 U.S. Department of Energy, NE-42 San Jose, CA 95125 Office of LWR Safety and Technology 19901 Germantown Road Barton Z. Cowan, Esq.

Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charles Thompson, Nuclear Engineer Pittsburgh, PA 15219 AP600 Certification NE-50 Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303

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