ML20198M929
| ML20198M929 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 11/17/1997 |
| From: | Joseph Sebrosky NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9801200165 | |
| Download: ML20198M929 (4) | |
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November 17, 1997
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Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis-Nuclear and Advanced Technalogy Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230 H
SUBJECT:
CONFIRMATORY ITEMS ASSOCIATED WITH CHAPTER 3.9.3 0F THE AP600 SAFETY EVALUA'il0N REPORT (SER)
Dear Mr. Liparulo The Civil Engineering and Geoscien:es branch of the Division of Engineering has provided an SER for Chapter 3.9.3.
However, the SER contained some confirmatory items.
These confirmatory items have been extracted from the SER and can been found in the enclosure to this letter.
You have requested that portions of the information submitted in the June 1992, application for design certification be exempt from mandatory public disclosure. While the staff has not completed its review of your reque!.. in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staff's final determination. The staff concludes that these follow on ques-tions do not contain those portions of the information for which exemption is
,cught. However, the staff will withhold this lettar from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staff's conclusions.
If, after that time, you do not request that all or portions of the information in the enclosures be withheld from public disclosure in accordan t with 10 CFR 2.790, this letter will be placed in the Nuclear Regulatory Commission Public Document Roon.
If you have any questions regarding this matter, you may contact me at (301) 415-1132.
Sincerely, original signed by:
Joseph M. Sebrosky, Project Manager Standardization Project Directorate Division of Reactor Program Management
')ffice of Nuclear Reactor Regulation Docket No. 52-003-Q(4
Enclosure:
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Ph. ' Nicholas J. Liparulo Docket-No.52-003 Westinghouse Electric Corporation AP600 j
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cc: ' Mr. B. A. McIntyra Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensing Westinghouse Electric Corporation Westinghouse Electric Corporation Energy-Systems Business Unit Energy Systems Business Unit P.O. Box 355 Box 355 Pittsburgh, PA 15230 Pittsburgh, PA 15230 Enclosure to be distributed to the following addressees after the result of the proprietary evaluation is received from Westinghouse:
Mr. Russ Bell Ms. Lynn Connor
- Senior Project Manager, Programs
. DOC-Search Associates Nuclear Energy Institute Post Office Box 34 1776 I Street, NW Cabin John, MD-20818 Suite 300 Washington, DC 20006-3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D.1 Sawyer, Manager 175 Curtner Avenue, MC-781 Advanced Reactor. Programs San Jose, CA 95125 GE Nuclear Energy 175 Curtner Avenue, MC-754 Mr. Sterling Franks San Jose, CA 95125 U.S. Department of Energy NE-50 Barton Z. Cowan, Esq.
19901 Germantown Road Eckert Seamans Cherin & Mellott Germantcwn, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP6CG Certification Mr. Frank A. Ross NE-50 U.S. Department of Energy, NE-12 19901 Germantown Road Office of LWR Safety and -Technology Germantown, MD 20874 19901 Germantown Road Germantown, MD 20874-Mr. Ed Redwell, Manager-F PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 m,
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- DISTRIBU" ION:
letter to Mr. Nicholas J. Linarulo. Dated: Nnvomh9r 17. 1997
- 0ocket>#4len* Enclosure to be held for 30 days
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l Confirmatory Items Associated with Chaptet 3.9.3 210.232F In the July 25, 1994 respo,ase to Q210.68, Westinghouse agreed to revise Section 3.9.3.4 and Tables 3.9-9 and 3.9-10 of the SSAR to state that the maximum allowable stress for supports of active components will be held to ASME Level C.
In addition, the response agreed to revise WCAP 13054 to delete the exception to Sec-tion 3.9.3.II.3.a of the SRP. This was identified as DSER Confirma-tory Item 3.9.3.3-2.
In Revision 3 to the SSAR, Westinghouse revised Section 3.9.3.4 and Tables 3.9-9 and 3.9-10 to provide a commitment that the allowable stresses for supports for active components will be held to ASME Service Level C.
Revision 15 to the SSAR revised A)pendix 1A under RG 1.130 to provide this same commit-ment.
Westing 1ouse has provided the staff with a proposed revision to WCAP-13054, which contains this same commitment. The staff con-cludes that limiting the allowable stress of supports designed to the rules of Subsection hF of Section III of the ASME Code to the Service Level C limits will not result in support deflections significant enough tc prevent operability of supported active components, and is consistent with SRP 3.9.3.
Therefore, pending receipt of the revision to WCAP-13054, DSER Confirmatory Item 3.9.3.3-2 will be closed.
210.233F In the June 16, 1994 response to Q210.75, Westinghouse agreed to revise the SSAR, Appendix 1A and WCAP 13054 for RG 1.130, Posi-tion C.6.b to delete an unacceptable equation and just reference Appendix F of Section III of the ASME Code for allowable ioads for ASME Class 1 plate-and-shell-type supports designed by the load 4
rating method. The staff has endorsed the load rating method in Subparagraph F-1332.7 of Appendix F in lieu of the RG 1.130 guide-lines.
Therefore, pending receipt of the SSAR and WCAP 13054 revisions, this response was acceptable.
This was DSER Confirmatory Item 3.9..a.3-4.
Rcvision 15 to the SSAR revised Appendix 1A as discussed above, and is acceptable.
Westinghouse has provided the staff with a proposed revis bn to WCAP 13054 which agrees with the response to Q210.75, and the revised Appendix 1A. Therefore, pending receipt of the revision to the WCAP, DSER Confirmatory Item 3.9.3.3-4 will be closed.
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Enc 1osure
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