ML20203D365
| ML20203D365 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 12/10/1997 |
| From: | Huffman W NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9712160177 | |
| Download: ML20203D365 (3) | |
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Dec:mber 10, 1997 Mr. Mcholas 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 ITEMS ASSOCIATED WITH THE AP600 SAFETY EVALUATION REPORT (SER) ON THE REACTOR COOLANT SYSTEM I
Dear Mr. Liparulo:
The Reactor Systems Branch of the U.S. Nuclear Regulatory Commission has provided its SER input to the Standardization Project Directorate on the AP600 reactor coolant system which will form part of SER Chapter 5. The input has open items which have been extracted and desig-nated as FSER open items 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 t
Office of Nuclear Reactor Regulation Docket No.52-003
Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION:
Docket File -
PDST R/F TQuay PUBLIC TKenyon WHuffman JSebrosky DScaletti JNWilson ACRS (11)
WDean,0 5 E23 JMoore,0-15 818 GHsil, O 8 E23 RCaruso,0-8 E23 TCollins,0-8 E23 SNewberry,0 8 E2 GHolahan,0-8 E2 f
- DOCUMENT NAME: A:CHS-SRXB.Ol To receive a copy of this document, indicate in the box: "C"=,
without attachment / enclosure
- E" = Copy with cttachment/ enclosure "N" = No copy
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OFFICE -
PM:PDST:DRPM l BC:SRXB:DSSA l D:PDS UDFfPM l l
7}WCHuffmarkdGCA TCollins */7 TRQuhy NAME 126097 12Fe/97 12/p /97 DATE g3 OFFICIAL RECORD COPY _
...a 7 9 in p e m g "g 9712160177 971210 lll PDR ADOCK 0520,00,03 c
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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 i
P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. Cindy L. Haag Ms. Lynn Connor Advanced Plant Safety & Ucensing 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 Germentown 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 Gesantown Road Barton Z. Cowan, Esq.
Germantown, MD 20874 Eckert Seamans Cherin & Mellott 600 Grant Street 42nd Floor Mr. Charies 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 4
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v CHAPTER 5 SEEGREBNTDEDESBGCAREE RGERHACIDOEU9FB5EEEBRANCH 230.140F Chemical and Volume Control System (CVS) Piping Classification in the SRXB evaluation of the RCS piping in SER Section 5.4.3, Open item 230.140F was repeated. SRXB agrees with the previous ataff position that the CVS piping is part of the reactor coolant pressure boundary and should be designed and constructed in accordance with the guidelines of Regulatory Guide 1.26. This FSER Open item is already being tracked by Westing-house (OITS# 6039). The Open item has been identified in this letter to reinforce the importance of an acceptable rrsolution to this issue.
440.758F Because the nil-ductility reference temperature of the reactor vessel mah rial increases as exposure to neutron fluence increases due to neutron embrittlement effect, the operating P/T limit curves need to be periodically adjusted to accommodate the actual shift in the nil-ductility temperature. The RCS P/T limit curves for heatup, cooldown, etc, are specited in the Pressure.
Temperature Limits Report (PTLR) as required in the AP600 Technical Specification LCO 3.4.3.
The RNS relief valve setpoint of 563 psig was sized with the RCS P/T limit of 621 psig, which is based on bounding P/T hestup and cooldown curves for the AP600 plant developed with a 54 effective full power years (EFPY), corresponding to a 60 year design life with 90 percent availability. For plant operation greater than 54 EFPY, or if the P/T curve is revised, the relief valve set point must be re-evaluated. The SSAR should be revise to include this as a COL action item 440.759F The main steamline flow restrictors have an effective nozzle throat area of 1.4 ft each, which is
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considerably less than the main steam piping area, and are credited in the Chapter 15.1.5 design basis analysis of a steam system piping failure to limit the maximum steam flow for a break at any location. The flow restrictors must be included in the ITAAC for verification of the as-built steam generator system. In a letter to NRC (B. McIntyre to T. Quay, " Response to Follow On Question RAI 640.106 Regarding the AP600 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) " NSD NRC-97 5412, dated November 4,1997), Westinghouse provided a draft revision to the Design Desrription and the ITAAC to include an inspection to verify the installation of the SG flow limiting orifice having the flow area less than 1.4 sq. ft. Incorporation of the draft material into the Design description and ITAAC is a confirmatory open item.
Enclosure i
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