ML20203C333
| ML20203C333 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 12/08/1997 |
| From: | Scaletti D NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9712150283 | |
| Download: ML20203C333 (3) | |
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Deceraber 8,1997 Mr. Nicholas J. Uparuto, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
REQUEST FOR CLARIFICATION OF CERTAIN REQUEST FOR ADDITIONAL INFORMATION (RAI) RESPONSES
Dear Mr. Upan lo:
As a result of the staff's continuing review of the AP600 WGOTHIC power control system (PCS) model, the Westinghouse responses to several RAls were determined to provide inadequate information upon which to decide the technical adequacy of the PCS heat and mass t vnsfer correlations and evaporated flow calcu;ation procedure. Please provide the missing information or the clarification noted below for the following RAI responses:
480.873 RAI response does not answer question. Provide the requested comparison.
480.905 The RAI response states the Zuber-Staub model is no longer the basis for the empi-ical Westinghouse flow stability model, contradicting the discussion presented in WCAP 14407 Revision 1, Appendix 7-A2,A3. Please clarify RAI response to address how existing databases or theoretical underpinning justifies the WEC assumption that hot, dry surfaces rewet.
480.908 RAI response does not address the technicalissue, and WCAP-14407 Revision 1 eliminated the figures in question. Pleass restore these figures, and aid the reo9sted information to allow the effect of heat flux on film stability to Le evaluated.
The revised RAI response should also clarify the data presented on page 7-16 and Figure 7-5 of WCAP-14407, Revision 1, i.e., quantify the phrase "were close to imin," or explain why the presence of runoff flow guarantees that i > Imin. The modelis based on the assumed behavior beyond the point of 1.1s' ability. If this assumption is not corrrrct, then Figure 7-5 is incorrect. Please add additional information to justify this approach.
480.992 RAI response assumes the applicability of Chua and Seban correlation. Not
.o considered is the importance of a 4 percent change in nyerall heat transfer coefficient on the peak pressure predicted by WGOTHIC for AP600.
480.1027 This RAI response uses the Chun and Seban corrclation to back out an effective film thickness for AP600. It does not respond to the original RAI, which requested a comparison of the 0.005 in. scaling film thickness to the film thicknesses observed in the Wisconsin and Chun and Seban data.
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Mr. Nicholas J. Liparulo December 8, 1997 in their RAI response, Westinghcuse referenced Kutateladze and Mudawar data, without presenting this data graphically. In their amended RAI response, WEC should summarize all of the referenced data (with an identifier to specify the data source and whether the data is for evaporation or condensation) in a single figure which compares Wisconsin, Chun and Seban, Kutateladze and Mudawar data. Error bars should be included, *vhere the data is available. This figure should compare the data to the AP600 liim thickness predicted using the Nusselt model at the top and bottom of the sidewall, if you have any questions regarding this request, please contact me at (301) 415-1104.
Sincerely, s
original signed by:
Dino C. Scaletti, Project Manager-Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 cc: See next page D(STRIBUTION:
Docket File PDST R/F JWRoe PUBLIC DMatthews TRQuay TKenyon WHuffman JSebrosky DScaletti JNWilson JMoore,0-15 B18 WDean,0-5 E23 ACRS (11)
DOCUMENT NAME: A:\\WLETTER.DCS To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PM:PDST:DPRM D:PDST:DRP,M NAME DCScaletti:sg TRQt[dy[
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Mr. Nicholas J. Liparuto Docket No.52-003 Westinghouse Electric Corporation AP600 cc:
Mr. B. A. McIntyre Mr. Rt.ss Bell Advanced Plant Safety & Licensing Senior ?roject Manager, Programs Westinghouse Electric Corporation Mclear Energy Institute Energy Systems Business Unit 1776 l 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 3.
Energy Systems Business Unit Cabin John, MD 20818 Box 355 Pittsburgh, PA 15230 Dr. Craig D. Sawyer, Manager Advanced Reactor Pm, rams 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 Germantowii, 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 Tea,hnology 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 Rodweli, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 l
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