ML20217B085
| ML20217B085 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 09/09/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9709230224 | |
| Download: ML20217B085 (3) | |
Text
a September 9, 1997 l
Mr. Nicholas J. L%aruto, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 j
Pittsburgh, PA 15230
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) ON THE AP600 STANDARD i
SAFETY ANALYSIS REPORT (SSAR) CHAPTER 15 ACCIDENT ANALYSES
?
i
Dear Mr. Liparuto:
The Nuclear Regulatory Commission (NRC)is still rey! ewing the AP600 Chapter 15 Accident i
Analyses. Based on recent discussion between the staff and Westinghouse on increases in reactor coolant system inventory events, the staff has determined that additional information will 4
be needed to complete its review of Chapter 15. The staff's RAl on the Chapter 15 analyses are l
provided as an enclosure to this letter, j
If you have any questions regarding this matter, you may contact me at (301) 4151141.
Sincerely,
)
i l
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 4
Enclosure:
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DATE 09/5 /97 09/f / W v' 09/81/97 9709230224 970909
'FiclAL RECORD COPY PDR ADOCK 05200003 PDR
t Mr. B. A. McIntyre Docket No. 52 003 Westinghouse Electric Corporation AP600 cc:
Mr. Nicholas J. Liparulo, Manager Mr. Ronald Simard, Director Nuclear Safety and Regulatory Activities Advanced Reactor Prograrns Nuclear and Advanced Technology Division Nuclear Energy Institute Westinghouse Electric Corporation 1776 Eye Street, N,W.
P.D. 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 Mr. James E. Quinn, Projects Manager LMR and SBWR Programs Mr. S. M. Modro GE Nuclear Energy Nuclear Systems Analysis Technologies 175 Curtner Avenue, M/C 165 Lockheed Idaho Technologies Company San Jose, CA 95125 Post Office Box 1625 Idaho Falls,ID 83415 Mr. Robert H. Buchholz GE Nuclear Energy Mr. Sterling Franks 175 Curtner Avenue, MC 781 U.S. Department of Energy San Jose, CA 95125 NE 50 19901 Germantown Road Barion Z. Cowan, Esq.
Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Frank A. Ross Pittsburgh, PA 15219 U.S. Department of Energy, NE-42 Office of LWR Safety and Technology Mr. Ed Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Mr. Charles Thompson Nuclear Engineer Palo Alto, CA 94303 AP600 Certification NE 50 19901 Germantown Road Germantown, MD 20874
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U.S. NUCLEAR REGULATORY COMMISSION REQUEST FOR ADDITIONAL INFORMATION ON WESTINGHOUSE AP600 GSAR CHAPTER 15 ACCIDENT ANALYSES 4
increases in Reactor Coolant Inventory RAI 440.725 In the conference call on September 4,1997, Westinghouse stated that sensitivity studies were performed to identify the worst cases for the inadvertent operation of the CMTs event and the inadvertent operation of the CVS event as discussed in AP600 SSAR Sections 15.5.1 and 15.5.2, respectively. Please provide information in the SSAR on these sensitivity studies and justify tha' the cases presented in the SSAR are the limiting cases, in addition, Westinghouse stated that in the analysis of the inadvertent operation of CMTs event, about 7 percent of the tubes in the PRHR heat exchanger (HX) were assumed to be plugged to minimize the PRHR i
heat transfer. Please document this assumption in the SSAR and discuss what controls cr procedures will be used to ensure the 7 percent limit on the tube plugging in the PRHR HX is not
- exceeded, j
i 1
Enclosure