ML20137D951

Forwards Comments on Guidelines for Determining Plant Seismic Margins,Per 781117 Request

ML20137D951
Person / Time
Site:	Davis Besse, 05000000
Issue date:	01/22/1979
From:	Fraley R Advisory Committee on Reactor Safeguards
To:	Knight J Office of Nuclear Reactor Regulation
Shared Package
ML20136A555	List: IA-85-363, Submits Topics for Discussion at Commission 830708 Meeting W/Acrs.Topics Include Seismic Design Margins ML20136A550 ML20136E176 ML20136E418 ML20136E423 ML20136E621 ML20136E929 ML20136F618 ML20137D336 ML20137D440 ML20137D455 ML20137D472 ML20137D477 ML20137D494 ML20137D511 ML20137D540 ML20137D551 ML20137D557 ML20137D562 ML20137D570 ML20137D576 ML20137D583 ML20137D588 ML20137D598 ML20137D601 ML20137D609 ML20137D616 ML20137D621 ML20137D627 ML20137D635 ML20137D641 ML20137D646 ML20137D652 ML20137D659 ML20137D665 ML20137D670 ML20137D849 ML20137D867 ML20137D881 ML20137D911 ML20137D924 ML20137D951 ML20137D978 ML20137E016 ML20137E026 ML20137E044 ML20137E056 ML20137E065 ML20137E075 ML20137E098 ... further results
References
FOIA-85-363 NUDOCS 8508230095
Download: ML20137D951 (2)

Text

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UNITED STATES 3."T[(f. 8 T

g NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 4, s,9 January 22, 1979 TO:

James P. Knight, Assistant Director for Engineering, DSS FROM:

Raymond F. Fraley, Executive Director, Advisory Committee on Reactor Safeguards

SUBJECT:

ACRS COMME?RS ON GUIDELINES FOR DETERMINING SEISMIC MARGINS AT DAVIS-BESSE NUCLEAR POWER ' STATION LNIT NO.1

'Ihe attached comments en the guidelines forwarded with your letter of November 17, 1978 to Dr. David Okrent have been provided by members of the ACRS in response to your request.

"y%

-l Ra rxl F. Fraley Executive Director

Attachment:

As stated cc:

H. Denton, NRR R. Savio, ACRS R. Wright, ACRS D. Okrent FILE:

EEP-2 8508230095 850722 PDR FOIA DELL 85-363 PDR d

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COMMENTS ON PROPOSED GUIDELINES FOR DETERMINING SEISMIC MARGINS AT DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 I

1.

It is not clear as to the extent to which safety related instruments and the control room (as related to safe shutdown and residual heat removal) are considered in this analysis.

2.

It is not clear as to the extent to which failures of non-safety graded equipment which might compromise safe shutdown and residual heat removal will be considered in this analysis.

3.

The tabulation in Item 7-A of Attachment 2 should be expanded to in-clude the parameter:

(Stress Allowable) - (Total Stress) l Seismic Stress O

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