ML20203C323
| ML20203C323 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 11/04/1997 |
| From: | Kenyon T NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9712150281 | |
| Download: ML20203C323 (4) | |
Text
November 4,1997 Mr. Nichol s J. Liparuto, M: nager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Analysis Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO OPEN ITEMS ON THE AP600
Dear Mr. Liparulo:
As a result of its review of the June 1992 application for design certification of the AP600, the staff has prepared the final safety evaluation report (FSER) for Section 13.3 of the AP600 Standard Safety Analysis Report (SLAR). The FSER identifies 2 open items needing resolution by Westinghouse before the staff can complete its review of this SSAR section. The open items are identified in the enclosure with tracking numbers associated with them.
You have requested that portions of the information submitted in the June 1992 application for design certification be exemp, from mandatory public disclosure. While the staff has not completed its review of your request in accordance with the requirements of 10 CFR 2.790, that portion of the submitted information is being withheld from public disclosure pending the staffs final determination. The;taff concludes that the enclosure does not contain those portions of the information for which exemption is sought. However, the staff will withhold this letter from public disclosure for 30 calendar days from the date of this letter to allow Westinghouse the opportunity to verify the staffs 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 accordance with 10 CFR 2.790, this letter will be placed in the NRC's Public Document Room.
If you have any questions regarding this matter, you can contact me at (301) 415-1120.
Sincerely, original signed by:
Thomat J. Kenyon, Proj.ect Manager Standardization Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No.52-003 DISTRIBUTION: See next page
Enclosure:
As stated
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Mr. Nicholas J. Liparuto Docket No.52-003 Westinghouse Electric Comoration AP600 cc:
Mr. B. A. McIntyre Ms. Cindy L. Haag Advanced Plant Safety & Licensing Advanced Plant Safety & Licensing Westinghouse Electric Corporation Westinghouse Electric Corporation Energy Systerns 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 l Street, NW Cabin John, MD 20818 Suite 300 Washington, DC 20006-3706 Mr. Robert H. Buchholz GE Nuclear Energy Dr. Craig D. 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 Germantown, MD 20874 600 Grant Street 42nd Floor Pittsburgh, PA 15219 Mr. Charles Thompson, Nuclear Engineer AP600 Certification Mr. Frank A. Ross NE 50 U.S. Department of Energy, NE-42 19901 Germantown Road Office of LWR Safety and Technology Germantown, MD 20874 19901 Germantown Road Germaritown, MD 20874 Mr. Ed Rodwell, Manager PWR Design Certification Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 l
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o OPEN ITEMS ON SSAR SECTION 13.3 100.32F Appendix 1 A of the SSAR indicates that Regulatory Guide (RG) 1.101 is not applicable to the AP600 standard design. Westinghouse states that Section 13.3 of the SSAR indicates that emergency planning is the responsibility of the Combined License Applicant and no reference to RG 1.101 will be added. The
- taff disagrees. RG 1.101, Revision 2, references NUREG 0654/ FEMA REP 1, and item 11.H. " Emergency Facilities and Equipment," of NUREG-0654/ FEMA-REP 1 is applicable to the TSC, OSC, and Decontamination Facility identified in the AP600 design. Westinghouse should reference RG 1.101, Revision 2, as applicable to the AP600 design.
100.33F Because of the unique design 'of the AP600, the habitability system for the Technical Support Center (TSC) is not the same as for the Main Control Room (MCR). At currently operating reactors, the TSC habitability system is either the same as for the MCR or the TSC has been provided a separate habitability system. At these sites, should the TSC become uninhabitable, it is usually evacuated to either the MCR or another location onsite where habitability can be estaDi!shed. Not having the TSC in the same habitability envelope as the MCR, as discussed above, increases the likelihood that the TSC will have to be evacuated. In addition, Westinghouse has indicated that should the TSC become uninhabitable, the functions and staff will be relocated to the Emergency Offsite Facility (EOF), and not the MCR or another facility onsite where habitability can be established. Consequently, the EOF will have to be activated and staffed early in order to assure that the functions and support provided to the MCR by the TSC are not impeded. Westinghouse should provide a COL Action item to staff the EOF at an " Alert" emergency classification level (rather than a " Site Area Emergency," which is the current practice) and the response to RAI 100.10 (a),
(b), (c), (d), and (f) should be incorporated into the AP600 SSAR.
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Enclosure
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DISTRIBUTION: Letter to Mr. Niqholas J. Lloaruto. Dated: November 4,1997
' Docket File
- Enclosure to be held for 30 days
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