ML20062F834

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Forwards Eval by Gs Lellouche of EPRI Using WASH-1400 Methodology Which Concludes That Addition of Relief Valves in PWRs to Relieve Pressure Surges from ATWS May Increase Risk to Public
ML20062F834
Person / Time
Site: Davis Besse  Cleveland Electric icon.png
Issue date: 12/12/1978
From: Mattson R
Advisory Committee on Reactor Safeguards
To: Crocker L
Office of Nuclear Reactor Regulation
Shared Package
ML20062F830 List:
References
781011, NUDOCS 7812210175
Download: ML20062F834 (1)


Text

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Docket flos. 50-500/501 I

f1EMORANDUM FOR:

L. P. Crocker, Technical Assistant to the Director, DPM FROM:

R. J. Mattson, Director, Division of Systems Safety, URR

SUBJECT:

SAFETY IlWLICATIONS OF ADDITIONAL STEAM RELIEF VALVES FOR DAVIS BESSE UNITS 2 AND 3 Enclosed is our response to an ACRS recuest fer an evaluation of the sa'ety implications of additional steam relief valves for Oavis Sesse 2 and 2.

Specifically, we were to provide a quantitative comparison of the advantages O

provided by the additional relief capacity versus the disadvantages of the added valves. Reference was made to work performed by Mr. Lellouche of EPRI concerning ATWS, which suggests that added valves actually increase j

the risk to the public.

7 The referenced work by Mr. Lellouche is not relevant since it deals with the primary system relief valves and discusses the possibilities of increased small LOCA risk. The valves proposed for Davis Besse are in the secondary steam system. There is no increased small LOCA risk l.

associated with these valves.

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Roger J. Mattson, Director L

Division of Systems Safety As Stated cc:

H. Denton E. Case R. Boyd R. Tedesco D. Ross T. Novak S. Israel G. Mazetis M. Rubin

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Contact:

Mark Rubin, NRR 49-27591 E

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