ML20203C409
| ML20203C409 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 12/08/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| FACA, NUDOCS 9712150298 | |
| Download: ML20203C409 (3) | |
Text
Decemb::t 8,1997 Mr. Nicholas J. Liparulo, Manager.
Nuclear Safety and Reguistory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
OPEN ITEMS ASSOCIATED WITH THE AP600 SAFETY EVALUATION REPORT (SER) ON THE REACTOR SYSTEMS TEST PROGRAfA
Dear Mr. Liparulo:
The Reactor Systems Branc. Of the U.S. Nuclear Regulatory Commission (NRC) has provided its SER input to the Standardization Project Directorate on the AP600 reactor systems testing program as part of SER Chapter 21. The input has open items which have been extracted and designated as FSER open items in the enclosure to this letter, if you have any questions regarding this matter, you may contact me at (301) 4151141.
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 DISTRIBQT1QB.
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DOCUMENT NAME: A: TEST PXS.OI To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with cttachment/ enclosure "N" = No copy OFFICE PM: POST:DRPM l BC:SRXB:QSSAI D:PDST:DRPM_ l l
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n Mr. Nicholas J. Liparuto 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 i
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 Dr. Craig D. Eawyer, Manager Advanced Reactor Programs Mr. Sterling Franha GE Nuclear Energy U.S. Department cf Energy 175 Curiner 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 8
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CHAPTER 21 SER OPEN ITEMS ASSOCIATED WITH 1 HE AP600 REACTOR SYSTEMS TESTING PROGRAM 440.74CF Westinghouse submitted the OSU test program final data report (WCAP 14252)in May 1995 and the complete test analysis report (WCAP 14292, Rev.1) for the program in September 1995. All OSU APEX test documentation has been submitted. The staff has completed its review of the data and analysis for the test program; Westinghouse has also responded to the most of the staffs RAls on these reports; however, three RAls,440,573,440.575, and 440.580, concoming WCAP 14292, Rev.1, remain unanswered. Consequently, the review of the OSU/ APEX test program remains open, pending submittal of acceptable responses to the three outstanding RAls.
440.747F The staff has reviewed WCAP 14727,"AP600 Scating and PIRT Clostre Report," Rev.1, including Westinghouse's responses to staff and ACRS questions. The staff has determined that most of the questions have been acceptably addressed. However, the staff has concluded that additional discussion is needed in the report to explain the differences between the " data" based and " hand calculation"-based values of the "pi" groups in the report. These values often differ by up to an order of magnitude, and use of the "pi" values based on data could give somewhat different results in comparing the response of the test facilities to that of the AP600. The staff understands that the hand-calculated values of the "pi" groups were used to keep the AP600 on a consistent basis with the test facility (since there are no " data" values, aside from nominal geometric parameters) for the actual plant. However, the " hand calculation" method requires the use of simplified models, e.g., two-phase flow and pressure drop, which may not reflect actual facility (or plant) behavior. One of the staffs primary objectives in requesting the " closure" report was to evaluate the actual data produced by the facilities in terms of consistency with the importance (rank) assigned to local and system phenomena in the PIRTs. The staff requests that Westinghouse provide additional discussion of the data related values of dimensionless groups, both in comparicon to the " hand calculated values" and in relation to the ranking in the PIRTs.
Enclosure 3