ML20134N583
| ML20134N583 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 02/19/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9702240273 | |
| Download: ML20134N583 (3) | |
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FeDruary 19, 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:
ANALYSES TO SUPPORT AP600 PASSIVE RESIDUAL HEAT REMOVAL EXCHANGER HEAT TRANSFER CORRELATIONS
Dear Mr. Liparulo:
In a Nuclear Regulatory Commission (NRC) letter to you on January 16, 1997, the staff noted the need for additional information to support the use of the heat transfer correlations employed by Westinghouse to model the performance of the AP600 PRHR heat exchanger. The information requested consists of comparison of your PRHR heat transfer correlations with data obtained using a "C"-tube heat exchangr.r.
In the January 16, 1997 letter, we also stated that we would provide you.:ata from the NRC's confirmatory tests at the ROSA /AP600 test facility, which were to be used to validate your models.
Upon further consideration, the staff has concluded that it is inappropriate to mandate the source of data for Westinghouse to use in this effort.
It is incumbent upon Westinghouse, as the AP600 design certification applicant, to determine the source and specifics of the data used to confirm or validate AP600 design characteristics and analytical models.
If you decide to pursue use of the NRC's confirmatory tests at the ROSA /AP600 test facility, we are willing to provide you with data from that facility.
The staff reiterates that additional analyses are needed to support the use of i
the heat transfer correlations utilized to evaluate the performance of the AP600 PRHR heat exchanger. The 3-tube PRHR test data comprise an insufficient 1
basis to allow the staff to confirm Westinghouse's conclusions. Additional data should be obtained by Westinghouse from testing in a bundle geometry prototypic of the AP600 "C"-tube heat exchanger, and which spans the range of
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operating and accident conditions anticipated in the AP600 design. The O
selection of data should be justified, and provided to the staff for review and approval prior to performing the analyses.
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Mr. Nicholas J. Liparulo February 19, 1997 If you have any questions regarding this matter, you can contact me.at (301) 415-1141.
S'incerely, orkginal signed, by:
William C.-Huffman, Project Manager p
Standardization Project. Directorate Division of Reactor Program Management Officefof Nuclear Reactor Regulation Docket No.52-003
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i Mr. Nicholas J. Liparulo Docket No.52-003 West (nghouse Electric Corporation AP600 1
cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director Advanced Plant Safety & Licensing Advanced Reactor Programs Westinghouse Electric Corporation Nuclear Energy Institute i
Energy Systems Business Unit 1776 Eye Street, N.W.
P.O. Box 355 Suite 300 Pittsburgh, PA 15:30 Washington, DC 20006-3706 j
Mr. John C. Butler 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 1
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 I
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 i
Germantown, MD 20874 Germantown, MD 20874
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