ML20198R601
| ML20198R601 | |
| Person / Time | |
|---|---|
| Site: | 05200003 |
| Issue date: | 10/27/1997 |
| From: | Scaletti D NRC (Affiliation Not Assigned) |
| To: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 9711130331 | |
| Download: ML20198R601 (3) | |
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October 27, 1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Analysis Nuclear and Advanced Technology Division Westinghouse Electric Corporation P.O. Box 355 Pittsburgh, PA 15230
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATIVE TO OPEN ITEM IN THE AP600 DESIGN CERTIFICATION REVIEW
Dear Mr. Liparulo:
As a result of the staff's continuing review of 'he AP600 design certification application, the Plant Systems Branch has prepared the draft safet) evaluation report (DSER) of Section 15.7.3 of the AP600 Standard Safety Analysis Report (SSAP). The DSER identifies one issue needing resolution by Westinghouse before the staff can complete its re"Nw of this section. The issue is identified in the enclosure, if you have any questions regarding this request, please contact me at (301) 415-1105.
Sincerely, 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
Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION:
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Mr. Nicholas J. Liparulo Docket No. 52 003 Westinghouse Electric Corporation AP600 cc:
Mr. B. A. McIntyre Mr. Russ Ball Advanced Plant Safety & Licensing Senior Project Manager, Programs Westinghouse Electric Corporation Nuclear Energy Institute Energy Systems Business Unit 1776 l Street, NW P.O. Box 355 Suite 300 Pittsburgh, PA 15230 Washington, DC 20006-3706 Ms. 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 Dr. Craig D. Sawyer, Manager Advanced Reactor Programs Mr. Sterling Franks GE Nuclear Energy U.S. Department of Energ.>
175 Curtner Avenue, MC-754 NE 50 San Jose, CA 95125 19901 Germantown 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 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 Rodwell, Manager 19901 Germantown Road PWR Design Certification Germantown, MD 20874 Electric Power Research Institute 3412 Hillview Avenue Palo Alto, CA 94303 f
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SSAR SECTION 15.7.3 OPEN ITEM 410 320F Offsite Radioloalcal Conseauences of Llauld Tank Faiiure: The staff has reviewed the liquid tank failure accident in accordance with SRP Section 15.7.3, " Postulated Radioactive Releases due to Liquid Containing Tank Failures." The acceptance criteria specified in the subject SRP section are based on meeting the following regulations:
1.
General Design Criterion GDC 60 as it relates to the radioactive waste management system being designed to control release of radioactive materials to the environment, and 2.
10 CFR Part 20 as it relates to radioactivity in effluents to unrestricted areas. The failure of the most limiting (i.e., in terms of offsite radiological consequences) liquid waste system (WLS) equipment outside the containment does not result in radionuclide concentrations in water at the nearest potable water supply in an unrestricted area exceeding the liquid effluent concentration limits for the corresponding radionuclides specified in 10 CFR, Part 20, Appendix B, Table 2, Column 2 or specific design features to mitigate the effects of failure are incorporated in the design of the WLS, if it does not meet the above require-ments of 10 CFR, Part 20.
F *eviously, the staff reviewed AP600 SSAR (Revision 0) Section 15.7.3 and found it acceptable.
The staff's finding was based on the proposed source terms and a commitment of COL action to evaluate site-specific offsite radiological consequences. Howeve', in the current SSAR (Revision 13) Section 15.7.3, Westinghouse removed all the content of the original SSAR and took a position deviating from SRP Section 15.7.3. Therefore, the previous SER finding is no longer valid.
The deviation is related to the safety analysis assumption stated in SRP Section 15.7.3 that credit cannot be taken for liquid retention by unlined building foundation. Westinghouse states that in the event cf a tank failure, the liquid would be directed to the auxiliary building sump. The basement of the auxiliary building is 6-feet thick and the exterior walls are sealed to prevent leakage. Westinghouse assumes that there is no release of the spilled liquid waste to the environment, and no radiological consequence analysis is needed; this is a deviation from SRP Section 15.7.3.
The staff has reviewed Westinghouse's justification for the deviation and finds it unacceptable, because Westinghouse did not consider the pessibility of concrete cracking in the auxiliary building foundations and did not provide any basis for its position. In addition, Westinghouse has not addressed the potential of auxiliary building seal deterioration. There is no leak testing, technical specification control, or surveillance requirement on the leak-tightness of the auxiliary building. Therefore, the staff has determined that taking credit of the building seal for the accident analysis is not acceptable. This is identified as an FSER Open item.
Enclosure
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