ML20235R289
| ML20235R289 | |
| Person / Time | |
|---|---|
| Site: | 05000601 |
| Issue date: | 09/29/1987 |
| From: | Kenyon T Office of Nuclear Reactor Regulation |
| To: | Johnson W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| References | |
| NUDOCS 8710070852 | |
| Download: ML20235R289 (4) | |
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September 29, 1987 Docket No. 50-601 s
Mr. W. J. Johnson Nuclear Safety Department Westinghouse Electric Corporation Water Reactor Division Box 355 Pittsburgh, Pennsylvania 15230 g
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Dear Mr. Johnson:
SUBJECT:
OPERATING BASIS EARTHQUAKE ZER0'PERF ACCELERATION VALUE FOR THE RESAR SP/90 l
During the staff's ongoing y uiew of PDA Modules 3 and 7 of the RESAR SP/90 application, the staff has noted in Appendix 2A of Module 3 and Section 3.7 of Module 7 that the Operating Basis Earthquake (0BE) Zero Period Acceleration L;
(ZPA) is specified at 0.1g, which is one third of the specific Safe Shutdown Earthquake (SSE)ZPAof0.3g.
When considering seismic issues, the staff relies upon criteria set forth in 10 CFR Part 100, Appendix A.
In particular,Section V.2 of 1b CFR 100,
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AppendixArequiresthemaximumvibratorygroundaccelerationcftheOperating Basis Earthquake (0BE) to be at least one half of that of the Safe Shutdown 1
Earthquake (SSE). However there have been cases where the applicant was j
permitted to assume an OBE (for seismic design criteria) which was less than 1
half of the SSE specified, (e.g. Diablo Canyon).
In these cases, the OBE Seismic Design Acceleration values were accepted on the' basis cf the site-specific regional se'ismicity and the resulting seismic hazard characteristic of the nuclear plant site.
However, since RESAR - SP/90 is a standardized nuclear reacter design, the seismic design parameters discussed in Module 3 (Appendix 2A) and Module 7 (Section 3.7) are not dependent upon power plant site conditions and should therefore be considered generic design parameters. Althouch. precedence has been set reoarding the use of an OBE (for seismic criterial which was less than half of the SSE on a case-by-case basis Westinghouse has not provided suf-ficient justification supporting a standard nuclear power plant design wi t such an OBE. Use of the parameter listed in your appl? cation for the OBE ZPA (0.19) under current regulations would severely limit pite locations within the contiguous United States.
Therefore, the staff requires additional justification to support an exemption request to Section V.2 of 10 CFR Part 100, Appendix A or a commitment to comply with that regulation.
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.Mr. Will'iam Schivley
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I September 29, 1987 Mr. W. J. Johnson If you wish to' set up a meeting or telecon to discuss resolution of this concern, call me at (301) 492-8206.
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t original signed by Thomas J. Kenyon, Project Manager Standardization and Non-Power Reactor Project Directorate Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:
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