ML20134B685
| ML20134B685 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/09/1985 |
| From: | Reinaldo Rodriguez SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| References | |
| RJR-85-400, TAC-59450, NUDOCS 8508160036 | |
| Download: ML20134B685 (2) | |
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$)SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 62o1 S Stseet, P.O. Box 15830 Sacramento CA 958521830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CAllFORNIA RJR 85-400 August 9, 1985 DIRECTOR OF NUCLEAR REACTOR REGULATION ATTENTION HUGH L THOMPSON JR DIRECTOR DIVISION OF LICENSING U S NUCLEAR REGULATORY COMMISSION WASHINGTON D C 20555 DOCKET 50-312 RANCHO SECO NUCLEAR GENERATING STATION UNIT NO 1 PIPING DESIGN CRITERIA The District is proposing to use a new ASME Code Case on damping values (N-411) at Rancho Seco.
This criteria is technically justified and provides a more realistic piping design.
The District has performed a 10CFR50.59 evaluation for the impact of this Code Case on piping systems and has determined that there are no unreviewed safety questions.
The District will update the " Updated Safety Analysis Report" to reflect this change. The District also commits to:
Use ASME Code Case N-411 in its entirety in any given piping seismic analysis.
In moving, modifying or eliminating piping supports, the District will not mix Code Case N-411 with other criteria such as Reg. Guide 1.61.
Use Pressure Vessel Research Committee (PVRC) approved damping values only in the response spectrum seismic analysis method and not in time history analysis.
Verify that as a result of using ASME Code Case N-411, if piping supports are moved, modified or eliminated, the expected increased piping displacements due to greater piping flexibility can be accommodated and there will be no adverse interactions with adjacent structures, components and equipment.
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. August 9,1985
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